ML20006B890
| ML20006B890 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/26/1990 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| Shared Package | |
| ML20006B891 | List: |
| References | |
| IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 9002060061 | |
| Download: ML20006B890 (4) | |
See also: IR 05000395/1989200
Text
_
_
__
.
.
<
...
.
.N
- .
]
.'
![ preop >
+
of
UNITED STATES
'i
NUCLEAR REGULATORY COMMISSION
~-
J
5
1l
wassiwntow, o, c.20sss
\\...../
l
u
.
u
January 26, 1990
s
Docket No. 50-395:
I
L
Mr. O. S. Bradham
-
i
'-
Vice President, Nuclear Operations
4
South Carolina Electric.8 Gas Company
n
Virgil C. Summer Nuclear Station-
1
P.O. Box B8:
'
Jenkinsville, South Carolina 29065
5
l:
i'
'
Dear Mr. Bradham:
i
-
.
!
SUBJECT: BULLETINS 79-02 AND 79-14. FOLLOW-UP INSPECTION REPORT 50-395/89-200
+
This letter transmits-the results of the follow-up inspection conducted by the
!
L
- Office of Nuclear Reactor Regulation (NRR) to verify compliance with Inspection -
!
L
andEnforcementBulletins(IEB)79-02,"PipeSupport-Baseplate-DesignsUsing
Expansion Anchor Bolts," and 79-14, " Seismic' Analysis for As-Built Safety-
i
-Related Piping Systems." This inspection was conducted from November.27'.
.
!
through December l',1989 and December.11 through 15, 1989 by a team composed of-
NRR staff and consultants.
'
l,
In reviewing South Carolina Electric and Gas (SCE&G) Company's effort regarding
~
,
IEB 79-02, the teani discovered that the computer program-used to verify anchor
I
bolt and baseplate sizing had not properly; accounted for anchor boltystiffness.
'
Excluding this one issue, the inspection team was satisfied that the: anchor.
~
bolts and baseplates had been properly designed and' constructed. Thus, SCE8G
l
.;
had complied with the bulletin.
,
i
,
With respect to IEB 79-14, the inspection team was satisfied-that the design
drawings properly reflected the as-built configuration of.the plant and that
the piping analysis calculations were readily auditable. Thus, compliance
-l
to IEB 79-14'was demonstrated. However, the inspection team identified
inconsistent modeling techniques used by different piping analysis contractors,
l
unconservative piping analysis modeling practices, and unjustified engineering
assumptione
.
a
,
'The deficiencies noted in Appendix A are considered-to be the most significant
?
l-
issues. identified during the inspection. Appendix B to the inspection report
,
contains minor discrepancies that appeared to the inspection team to be.
'
isolated errors with minimal safety significance. The Appendix B discre-
.i
pancies are listed for. completeness and they are expected'to be resolved
by SCE&G without the need for NRC inspection.
4
!
-
\\
.
t
,
- gg2ggggi $@8hp
e
.
.
4
-,
-w--
e
.w,
. , - -
..,eu-.-
, , .
..
-m.-
.. ,
a.-
,
,.4- - . . - ,
_
. . _ _ _ _ - _
_ .
. - .
. _ .
. - -
.
.
,
.
.
Mr. O. S. Bradham
-2-
January 26, 1990
..
In Appendix C, four issues were identified by the team that require additional
review by the NRC.
The' results of our review will be communicated to you
1
when they are available.
]
l
-SCE&G should individually track all items identified during the inspection such
that their formal resolution can be verified at a later date.
Please inform us of the date by which actions'.related to the open items identi-
fied in this report will be available for follow-up inspection. Some of the
4
identified items may be potential enforcement findings. Any enforcement
actions will be identified by Region 11 in separate correspondence.
In accordance with 10 CFR 2.790(a), a copy of this-letter and the enclosure
will be placed in the NRC Public Document Room.
-l
Should you have any questions concerning this inspection, please contact the -
NRR Project Manager, Mr. Jack Hayes or the inspection team leader
Mr. Ron Parkhill. Messrs. Hayes and Parkhill can be reached at (301) 492-1456
and(301)492-0963, respectively.
. Sincerely,
Original sign'ed by
Steven A. Varga, Director
Division of Reactor Projects I/II
Office of Nuclear Reactor Regulation
.
Enclosure:
Inspection Report 50-395/89-200
I
i-
- SEE PREVIOUS CONCURRENCE
RSIB:DRIS*
ESGB:DET*
EMEBDET* SC:RSIB:DRIS* C:RSIB:DRIS*
D:DRIS*'
RWParkhill:bt JSMa
AJLee
EVImbro
WDLanning
BKGrimes
01/24/90
01/26/9p
01/23/90 01/24/90
01/24/90
01/24/90
D:DET*
P
'
JERichardson
a
01/26/90
90
i
,
!
,
-
-
_
. _ _ _ - _ _
_ _ _ _ - _ _ - _ _ _ _ _ _ _
.a
.;
!
o .. L
.
3
'
y
L,
.
-Mr. O. S. Bradham-
-3-
January 26, 1990
'
'
t
!
- cc w/ enclosure:
a,
,
Mr.- William A. Williams, Jr.
'
h
Technical-Assistant - Nuclear Operations-
~ Santee Cooper
P.O. Box 764(MailCode.153)
?
Columbia, South Carolina 29218-
-
'J. B. Knotts, Jr. ,' Esq.
'
' Bishop,' Cook, Purcell-
and Reynolds-
l
1400 L_ Street, N.W.
'I
Washington,-D.C. :20005-3502
'
>
'
Perry C. Hopkins'
Resident Inspector /Sumer NPS
r
-c/o U.S. Nuclear Regulatory Comission
- 1
Route 1, Box 64
'i
Jenkinsv111e, South Carolina 29065
j
i
Stewart D. Ebneter-
Regional Administrator, Region II
U.S. Nuclear Regulatory Commission
101 Marietta Street, N.W., Suite 2900
'
Atlanta, Georgia 30323~
Chairman, Fairfield County Council
P.O. Box 293
Winnsboro, South Carolina .29180
Mr. Heyward G. Shealy, Chief
Bureau of Radiological Health
-South Carolina' Department of Health
and Environmental Control
2600 Bull Street
Columbia, South Carolina 29201
>
I-
South Carolina Electric and Gas Company
l~
Mr. A. R. Koon, Jr. .. Manager
.
Nuclear Licensing
.
,
. Virgil C. Summer Nuclear Station
1
-P.O. Box 88
Jenkinsville, South Carolina 29065
,
.,-
,
-
.
.s
.-
.
-
.
.
-
-
.
Mr. 0.:S. Bradham-
-- 4 - -
January 26,.1990
t
o
Distribution-
escastl.11es?.50F3963
RS I BTR/ F5""""^"'"**
DRIS'R/F'
!
'
TEMurley,' NRR
. JHSniezek, NRR
FJMiraglia, NRR-
,
FJHebdon, NRR
-j
BKGrimes, NRR
GClainas, NRR
,
WDLanning, NRR
t
EVImbro, NRR
.;
RWParkhill, hRR'
'
RSIB-Staff
SAVarga, NRR
JERichardson, NRR
-
JJHayes NRR
'!
EGAdensam, NRR-
GBagchi. NRR
PTKuo, NRR
LBMarsh, NRR .
.
l'
'JSMa, NRR
AJHLee, NRR
I
RLSpessard, AEOD
JJBlake, RII
FScantrell, Rll
RLPrevatte, SRI Summer.
-
Regional Administrators
'
Regional: Division Directors
l-
Inspection Team
LPDR
,
ACRS (3)
i
OGC-(3)
1
l
IS Distribution
.
.-
i
,
/
h
. - . -
-
.
l