ML19319B096
| ML19319B096 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/07/1974 |
| From: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001070649 | |
| Download: ML19319B096 (5) | |
Text
-.
i
-( }.
-c", l1 : -
MAY 7 1374 O ' Ne.
84 50-270 K coller, Assistant Director for Operating Reactors, Licensing V. Moore Assistant Director for Light Water Reactors, Croup 2 Licensing TRANSFER OF OCONEE NUCLEAR STATI0'i, UNITS 1 AND 2 FROM LVR 2-3 TO OR BRANCH 1.
Effective ir: mediately,' the Regulatory licensing responsibility for Oconee Nuclear Station,.Unita 1 and 2 (Docket Non. 50-269/270) is transferred from' LWR Branch 2-3 to Operating Reactors trrnch No.1.
{
oconee 15 nit 1 received a full-term, fullg ower operating ifcense, DPR-38, A February 6, 1973 and Oconee Unit 2 received a full-term, full-power operating license, DPR-47. on October 6, 1973. Both plants are currently operating and there are no operating power restrictions on either plant.
The LECDID (attachment.1) defines the generic item categories. The
~ status of the ' safety review for Oconee Units l'and 2 is surnarized in Attachment 2.- The attachment includes the status of generic
]
items as well as items specific to Oconee.
By copy of this nemo TR, RO, OPS, Regulatory Files, EP, OCC, Public i
Information and Public Proceedings are being notified of the following changes:
From
,T,0 0
Project Manager I. A. Peltier L. W.-McDonough Branch Chief A. Schwencer R. Purple i
Assistant Director V. A. Moore K. Coller-Licensing Assistant E. I. Coulhourne S. Teets "Drignni signed B3 5
- 3. Gi.-
m A. Gianbusso, Deputy Director for Reactor Projects 1
Directorate of Licensing
' Enclosures and :ce: See next page-L:
AGi busso I 5/
/74 l omes >
M-
. ORD I ALC/ WR 2-3,, L:,C/,0RB,1~_
LWRA2 LtAD/ ors N
BEN-f
,W g)?Q '
suanner > IAEel nkmL.UfcDonough._
.AS cer..
Ehrp.L KGollet ean m' 31.
h...D.4.. 51..l.0 __ D.4.. 3E.0..D.4.. 3L1.
1.7).31.. 3
/7,4_.s/ 3 /74 NN Qlade$5 YtY '
a-mm 8001070hk
[
y
K.' Goller.
V. !foore pg i 1974 Inclosures:
1.-'The LEGEND 2.
Status of Review Itema ece: TR ADe -
-OPS ITIhoc:pson, EP INilchine, OGC Otiles FKaras
-DISTRIBUTION:
Dockets (2)
LWR 2-3-Rdg-L Rdg IAPeltier ASchwencer VAMoore RPurple
- KGoller.
LMcDonough 7
AGiambusso RSBoyd EIGoulbourne STeets i
i i
~
y 1
l
+
u i
+
L
' !'"t,
3 --
3m.
_yyy
. ^;=
l
- X V.
r' X&
7y.
+
. #8 SumsentE >
^'
1 ante >
- Q-.
~
' :: 4 ' ;,.
i Foea AEC-Sia (An.9-53) ABCM 4340 (4,yyf,LTa^mieaaasEiorait '1Mt-i'is-50s.
- t j,.
cg;;ge
. e:.e
.l v'.
ww ny.:;
, x.
- 3-
+
?'y A V:
' yg 4 1974 :
. ge - g,.
7pr g;
+
MC..
~
LEGE:n
,s.
-1
- This item,has been evaluated in -light,of current requirements and A.
~ ?
ithe status.hss be n evalu ned as acceptable.
(This. does not.
inecessarilyLmean that the status fully ceets current requirements.)-
Thir, Lit?,nafbesnavahated i'i 1ipt of currmt requirrents and
~s seasur::N.cvnican.initined tat Jill aka tne ndus acceptale.
This'itcmthas not been evaluated in light of current requirements; 1C.
Lhowever,' the Project Manager's jucpnent is that the status;is t probably' acceptable., -(This judgr.ent should include consideration iof (a),wr. ether Regalatory requirements have been changed much since-L _ F th'e.itclia uaslevalusted, (b) whether the item has been evaluated g
at ~otcer plants:with Inis i;em similar, (c) uhether there' would be a substantial effect on public health and safety even if current requirectnts were r.ot cet ana any other relevant infort;ation known
- to the Project Manager.)
'This litea has not been ev_aluated in ~ light of current requirements.
' D.
It.is the Project Manager's judgment that the status is probably unacceptable.
p This ite: has not been_ evaluated in light of current standards.
t
~E..
cannot express a judgment concerning acceptability-The Project Manager lof'the status.
(This category included items for which the L
-Regulatory requirerents have not been determined.)
~
x
.- MA
^ This iten is not" applicable' to the facility..
..i r
2:
t y _
t W
^^I-l
+
4 f
f' 3
.g s.
.,s v'
4 n
,k--
.?
^
^
~
w:
R.
yl%:&
~
~
_4
TU '
T m
g.3 f
.- ?
-l
".J @ j III
~
.kAY-T 1974 ;
w Mrm
~
LS U ' f '-
Jn'h OF 78.7 lii_y31, UT # -
\\
M.
Generic Itenn Uhich h5vn neen Rm4olveel and naqutrg Ho Further Licensing Actions Reference _
.. It em_
2 Page 5-11 SER 7/6/73 51.fInstrumentationforEarthquake.(SCL1)
Page 12-6 SER 7/6/73 -
- Quality ' Assurance '.,r. 0pe. ration's Page'4-2 SER Suppl.. 3.7/10/73
- 2.:
.3; ' Steam Line Break Page 7 'O SCR 7/6/73
- 1
- 14. > Protection Against Pipe ' Whip Page 7-38 SER 7/6/73 '
cInside Containment; '.
- 5.
Combustible Gas in Containment Page 7-45 SER 7/6/73
. Post-Accident. Control _.
Page 54 SER 12/29/70 Ade.uacy.of Post-Accident Monitoring Page 9-17 SER 7/6/73
~ 6.:
q
~j'
_7' Post--Accident Control Room liabitability Tech Spec 4.12
~ ' '
Reliability' for Containment Isolation Page 45 SER 12/29/70
- 8. -
. Valve Closure Tech Spec 4.8 9.
Main Steam Isolation Valve Leakage S10.
Instrumentation Lines Penetrating Con-Tech Spec 4.4 tainment-(SG-11)
Adequacy of Inservice Inspection Program Page 29 SER 12/29/70 Page 5-11 SER 7/6/73
'11.
Page 6-1 SER 7/6/73,
~ 12.-
Adequacy'of Tornado Protection Page 3-10 SER 7/6/73
'13; Adequacy of. Flood Protection Page 5-4 SER 12/29/70
'14.
Operability of. Safeguards Equipment
~in Accident Environment
~
~
m 15. - Conformance of ECCS Interim Policy Page.7-1 SER 7/6/73 Statement 16
' Adequacy.of Testing When Disabling Page 8-1 SER 7/6/73 1
-Vital Equipment 17.
Adequacy of Power and Control Page 8-1 SER 7/6/73.
-(IEEE 279, 308, CDC 17, SG 6).
'.18.
Primary.and Secondary Systems Safety Page 5-9 SER 7/6/73 (and Relief Valve Support Adequacy
.SER Suppl.'l 8/2/73 c19.
Fuel Densification SER Suppl. 3 7/10/73-Page 7-34 SER 7/6/73
- 20.-- : Internal Flooding of. Critical Equipment 21'.
Primary-Coolant Leakage-Limits and Page: 32 SER -12/29/70 :
Detection Capability.
=22.
Furnace; Sensitized Stainless Steel Page 5-6 SER.7/6/73.
Page 5-10, 6-1 SER 7/6/73 l23. EScismic Design Adequacy
' Page 5-7 SER 7/6/73 c24. ; Fluence Damage to Reactor Vessel..
Tech-Specs 6.6
- 25.. Reporting Requirements-(SC -16 &L21):
, Page 12-3L SER 7/6/73 :
-26.; Adequacy of' Emergency Plan.(App. E)'.
Tech Specs Table 4.1,
.27. 1 Hydraulic: Pipe; Snubbers.
Page 7-38 SERl7/6/73 i
728 3'High-Energy.Line Modifications-
)
' s.
j.
,e m
\\
ht 4
.j 7
n u
l y~.
~
~-.
p.i u
- p;. i ?-
'l
.4'
.MM 7 E4.
. 5-
.s g, 7 '
.:e r
. # d '.. 'Q :"ve,y mgp.fy;..cJ,.
- .4
-M D.: L..'.
u.'.'
' 6M
. '_. ".'di,
- i z.-
Reference
[ftem?
,f.
t~
nl. Ad6quacy NU>Industt: 4:14mir ity~
Pvt;2 194 :D 7/6//t
- Marchl 21,:197411ctter to applicant requested reevaluation of secur1Ly.
cplan per RG 1.17. LApplicant revis'4 4/17/74.
OSn reviewing revision.
'.2. ' Performance.of-Effluent Treatment Systems Page 9-1 SER 7/6/73 7(ALAP):
Applicant-im revising unste 1:.aaagement system.
I'relin tuary design -
will be submitted.for.AEC review about nid 1974.
+
- 3. j Adequacyf of Environmental'!!onitoring Progran Page 9-18 SER 7/6/73
~ '
Tech Spec 4.11 1-AEC 'is; requesting. modification 'to Environmental Monitoring Tech l
Spec. Revised Spec to be completed June 1,.1974.
t 4.
Evaluhtion' of Refueling Cask Drop
'OR'Oill re-review this matter in mid 1974.
Legend C, D, E, NA Items LNA Items were not included on. lists femend'C Items-
~1. LTurbine'Overspeed
~
'2. ! Rod Drop Accident Analysis-
- 3. 2ECCS. Water Hammer Legend'!D Itces
=
J1.. Anticipate'd Transients Without Scram (ATWS), Page. 7-37 ' SER 7/6/73 J 2.'
-Main' Coolant; Pump Overspeed'SER Suppl. 2 10/1/73 iLegend-E Items-
_}UoncL Items-SpecificL o Oconee - legend! B Category t
- Iten Ref,erence.
s a
w Io'dinc1Filtiers in/SpentiFuell Building -
Page'10-1,111-2 SER;'7/6/P s
e 5
?
r
?. Ty,
- j..* l '
~
_ -' +-
.. ^
_ _ sc - t.
~,
?
-l a,.
.;f;._
t s
)
b.
1
~
e, 4
.g..
w:
.