ML19322B983
| ML19322B983 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/22/1971 |
| From: | Moseley N US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Henderson J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19322B984 | List: |
| References | |
| NUDOCS 7912200701 | |
| Download: ML19322B983 (2) | |
Text
. _ _ _ _ _ _ _.
/
UNITED STATES
[
ATOMIC ENERGY COMMISSION
/,
.I e
- }
DIVWON OF CCMPUANCE REGION 84 - sulT E 818 230 PE ACHT REE ST RE ET. NORT HWEST 7,L,,,,,,,
t,w,,,,,,,,
- 47 8 AT L A NT A. GEORGI A 30303 October 22, 1971 J. B. Henderson, Chief, Reactor Construction Branch (2)
Division of Compliance, Headquarters DUKE POWER COMPANY (OCCUEE 1), LICE'ISE NO. CPPR-33, DCCKET NO. 50-269 The attached report of an inspection on June 28 through 29, July 29 through August 1, and August h,1971, is forwarded for information. An item of nonec=pliance with Criterion VIII of Appendix 3 to 10 CFR 50 regarding traceability of installed piping and fitti Igs was identified during the inspection. This item of noncompliance was discussed in the letter con-cerning the inspection which was sent to the licensee.
The report discusses the inspector's observations and review of the con-tainment overpressure test. The inspector's review indicated that the test was conducted satisfactorily with no deficiencies identified.
The report discusses the measurement of valve vall thicknesses. We intend to pursue this subject additionally during future inspecticns with an in-tent to obtain evidence that the as-installed valve vall thicknesses meet minimum requirements.
Based en telephone conversations between Region II and Compliance Headquarters,
it is our understanding that the evaluation of the adequacy of the Oconee 1 centainment leak rate test vill be made by th,e Division of Reactor Licensing and/or the Division of Reactor Standards.
Region II understands that resolution of the centrol rod drive problem was referred to the Division of Peactor Licensing in a memorandum from Lov to Morris dated September 21, 1971. It is our belief that en engineering solution should be sought to resolve the problem of gas accumulation in the centrol rod drive housings.
If an engineering solution is impracticable and administrative controls are relied upon, technical specification re-quirements for these administrative actions are necessarf in cur view.
N. C. Meseley C0:II:NCM Senier Reactor Inspector
Enclosure:
C0 Ept. No. 50-269/71-7 (Murphy)
~70l
- ,7.912200 4
=
-=
r -
r
e o
- 7 I
J. B. Henderson Octoler 22, 1971 ec w/ encl:
E. G. Case, DRS (3)
H. R. Denton, DRS (2)
R. S. Boyd, DRL (2)
R. C. DeYoung, DRL (2)
D. J. Skovholt, DEL (3)
A. Gia=busso, CO L. Kornblith, Jn, C0 R. H. Engelken, C0 J. G. Keppler, CO J. P. O'Reilly, CC:I B. H. Grier, C0:III J. W. Flora, CO:IV R. W. Smith, CO:V j DR Central Files V
'y-p'l bf ',,/ h ;l.
ron Y\\
,f m tyg,. s /o;. /.
s.
, ' ) l-;
lJ Q,
vy lf
..., 19 [.A 7
1i
\\
'e
/
' C.,
"4-g.
\\%\\.
, ~ ;y
- %l
't h-w.n'
. C y
_