ML19309D911
| ML19309D911 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/07/1973 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19309D898 | List: |
| References | |
| NUDOCS 8004110741 | |
| Download: ML19309D911 (5) | |
See also: IR 05000313/1973007
Text
.
.
.
O
,.
.
j
p
A
2:'
(po"o.4['h
'
UNITED STATES
I
ATOMIC ENERGY COMMISSION
p
7( e) '
l !
1
DIRECTORATE OF REGULATORY CPERATIONS
-
'
.
accioNis - suit E sta
c,g ' /
230 P E AC Mf met St R E ET. NomT HwEST
,
- %ts o'
AT L. ANT A, GECmos A 30303
In Reply Refer To:
It0:II:MSK
JUN
71973
50-313/73-7
-
1
.
.
Arkansas Power and Light Company
Atta: Mr. J. D. Phillips
Vice President and Chief Engineer
Sixth and Pine Streets
Pine Bluff, Arkansas 71601
G< tiemen:
This refers to the inspection conducted by Messrs. M. S. Kidd and
K. W. Whitt of this office on May 8-11, 1973, of the activities
authorized by AEC Construction Permit No. CPPR-57 for the Arkansas
Nuclear One, Unit 1 facility, and to the discussions held with
Mr. J. W. Anderson and other members of your staff at the conclusion
of the inspection.
Areas examined during this inspection included previously identified
outstanding items, preoperational test procedures, your quality
assurance program for operations, audits of the preoperational
testing program, and the station log. Within these areas, the
inspection consisted of selective examination of procedures and
representative records, interviews with plant personnel, 'and
observations by the inspectors.
j
'
During this inspection, it was found that certain of your activities
appear to be in violation of the Code of Federal Regulations. These
{
activities and reference to pertinent requirements are listed in
'
Part I of the enclosure to this letter.
This no:. ice is sent to you pursuant to the provisions of Section 2.201
-
of the AEC's " Rules of Practice," Part 2, Title 10, Code of Federal
Regulations. Section 2.201 requires you to submit to this office
within 30 days of your receipt of this notice, a written
statement of explanation in reply including:
(1) corrective steps
which have been taken by you, and the results achieved; (2) corrective
steps which will be taken to avoid further violations; and (3) the
date when full compliance will be achieved.
\\} h
a
i
1
'\\
V
800\\110 7 N
.
_
_
-
-
. _ . . _ . _ _
_
_ _ _ _ _ _ _ _ _ _
_.. _
_
_ _ _ _ . _ . _ _ _ _
. _
. - . _ _
_ _ _ _ _ _ _ _
e
.
.
-
~
,
r
i
.
i
.
'
Arkansas Power and Light
-2-
!
J,UN
7 1973
comp.ny
1
i
i
Previously identified and new outstanding items are sunnarized in
Parts II through IV of the enclosure to this letter.
4
.
.
.
.
l
Should you have any questions concerning this letter, we will be glad
to discuss them with you.
4
i
Very truly yours,
!
5
)'NraanC.Moseley
'
n%
0
l
Director
1
!
Enclosure:
l
As stated
.
!
I
i
)
.
6
A
l
l.
l-
t
-
.
__ .._ ._.-
,
. _ . - _
- . _ _ _
. _ ,
__. _ _ - _ _ _ , . - . . _ _ _ . . . _ _ _
_
.
. . . .
.
.
.
.
.
_
.. .
.
.
,
.
.
'
<,
.
,
.
N
.
'
'
.
ENCLOSURE
DOCKET No. 50-313
.
.
I.
Enforcement Action
.
.
A.
Violations
.
Contrary to Criterion / of Appendix B to 10 CFR 50, approved
I
procedure QAP-4, " Review of Operating Procedur?.s and Test
Procedures," had not been used by the Safety Review Committee
in performing procedure reviews.
B.
Safety Items
None
II.
Licensee Action on Previously Identified Enforcement Matters
A. . Violations
1.
Gaseous Radwaste System Tank Volumes
The working pressure of the compressor and decay tanks in
the gaseous radwaste system will be increased to provide
the holdup capability stipulated in the FSAR.
2.
Reactor Building Spray System Electrical Test
All corrective action to be taken to preclude recurrence
of the violations of Appendix B to 10 CFR 50 resulting
,
from performance of this test had not been completed at
the conclusion of the inspection.
3.
Reactor Building Spray Piping
4
An evaluation of the significance of a crack found in the
-
reactor building spray system piping will be submitted per
10 CFR 50.55(e) by May 28, 1973.
B.
Safety Items
There were no previously identified safety items.
-
- -
..
. . .
_
_
__ _
.
-. . -
- -
. .
-
.
e
.
~
s.
, . ' ' '
'
m
,
'
-2-
,
,
III. New Unresolved Items
73 7/1 Arkansas Nuclear One Quality Assurance Program For Operations
OP 1004.15, " Arkansas Nuclear One Quality Control Program,"
-
does not define how the program requirements are implemented.
73-7/2 Licensee Review of Procedures
The licensee's procedure review committees do not employ
>
checklists or other aids in reviewing procedures.
.
IV.
Status of Previously Reported Unresolved Items
72-6/2 Staffina Commitments
'
j
Minimum staffing requirements outlined in the Unit 1 FSAR
,
have been met. This item is resolved.
'
72-9/1 Incorporation of All Safety Related Equipment in the FSAR Q-List
>
Not inspected.
i
!
72-9/3 Freparation of Test Procedures to Cover Tests in " Guide For
Planning of Preoperational Test Programs"
Test procedures to cover those tests discussed in RO Report
No. 50-313/72-9,Section IV, paragraph 4, have been identified
and most have been written.
,
.
73-1/1 Implementing Procedure For Use of Jumpers and Bypasses
'
i
,'
Ihis procedure was in the review process, with no change in
status from the previous inspection.
73-3/1 Completion of Construction of Radwaste Systems
Not inspected.
-
73-5/1 Reactor Building Ventilation System Tests
i
Additional comments were given on the procedure which will
be used to test this system.
l
l
73-5/2 Core Flood System Flow Rate Test
'
No change in status from previous report. Licensee personnel
do not feel this test is needed.
O
.
e
w
-,-
-~s
-- - ,
, -
- ,
-
r-
-
m-w w y
e
-e---e-=-----*-e=
1mme
4
er
w-W--=---==wte-'v-et---e+v-e-*
,
.
.
.
s
,.
.
Ltr to Arkansas Power and Light Company
4td
JUN
71973
cc v/ encl:
. D. Thornburg, R0
RO:HQ (h)
Directorate of Licensing (h)
DR Central Files
- PDR
- Local PDR
- NSIC
- DTIE, OR
- State
"To be dispatched with licensee response.
.