IR 05000313/1987028
| ML20235N506 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/24/1987 |
| From: | Fisher W, Terc N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235N476 | List: |
| References | |
| 50-313-87-28, 50-368-87-28, NUDOCS 8710060539 | |
| Download: ML20235N506 (4) | |
Text
_ _ _ _ _ _
_
-,
,
..s,
.
APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/87-28 Licenses:
Dockets:
50-313 50-368 Licensee:
Arkansas Power and Light (AP&L)
P. O. Box 551
'
Little Rock, Arkansas 72203 Facility Name:
Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At:
Russellville, Arkansas Inspection Conducted:
August 24-27, 1987
~
7 24/[87 Inspector:.
A N
N. M. Terc, Emergency Preparedness Specialist Date Nuclear Materials and Emergency Preparedness Branch J&
7kMD Approved:
<t i m W. L. Fisher, Chief, Nuclear Materials and Date'
Emergency Preparedness Branch Inspection Summary Inspection Conducted August 24-27, 1987 (Report 50-313/87-28; 50-368/87-28)
Areas Inspected:
Routine, unannounced inspection of licensee's emergency i
preparedness training program.
Results:
Within the areas inspected, no violations or deviations were identified.
0710060539 87i001 PDR ADOCK 05000313 G
,
!
!
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
. _ _ _ - _ - -
. h,
,
>
_,
DETAILS
!
1.
Persons Contacted Licensee
- S. Quennoz, General Manager, Plant Operations
- P. Michalk, Plant Licensing Engineer
- R. Lomax, Plant Licensing Supervisor
- F. Van Buskirk, Emergency Planning Coordinator
- D. Boyd, Emergency Planning Coordinator
- E. Ewing,. General Manager, Plant Support
- T. Baker, Technical Support Manager
- R. E. Jackson, Administrative Training Supervisor
- D. Snellings, Manager, Nuclear Programs D. Brinkley, Lead Emergency Plan Trainer NRC
- W. Johnson, Senior Resident Inspector
- Denotes those individuals present at the exit interview.
2.
Areas Inspected The inspection included interviews with cognizant individuals, observation
,
of activities, independent measurements, and record reviews.
The depth and scope of these activities were consistent with past findings and with the current status of the facility.
Except as noted, the inspection revealed no violations, deviations, deficiencies, unresolved items, or open items.
Notations after a specific inspection item identify the following:
I = item not inspected or only
-
partially inspected, V = violation, D = deviation, H = deficiency, i
U = unresolved item, and 0 = open item.
]
Procedure Areas Inspected and Inspection Requirements
{
82206 Knowledge and Performance of Duties (Training)
02.01 Adequacy of training program (The NRC inspector verified, by means of 6 interviews and 41 record reviews for three different emergency response organizational elements, that training was conducted in accordance with administrative Procedure 1063.21,
" Emergency Response Training Program." Classes were given in accordance with existing lesson plans.)
_ _ _ _ _ _ _ -.-
_ _ ___ -_-_ _ - _ -
-
.
.-.
_ - _ -.
p 7 2. a, ;..
L
h
02.02 Implementation of training program'(The NRC
'-
-inspector determined by review of 41 emergency response _ individual records that training / retraining was adequately accomplished.)
02.03 Understanding of authorities and responsibilities (The NRC-inspector verified by
,
- means of six key ~ personnel-(e.g., shift operations'-
L
'
supervisors.(S0S), shift administrative assistants, one' shift HP technician, and one HP supervisor) that'they understood their emergency
.
authorities and~ responsibilities and that they could perform ~their. assigned duties.)
02.04
- Proficiency in the use of post-accident-indicators (The.NRC inspector determined that the
licensee had committed to establish a' scheme to-properly use' core and containment indicators I
before January 1,-1987.)
02.05 Ability to classify eme'rgencies (The NRC inspector verified by means.of interviewing two 50Ss and'
two SAAs that they.could use existing emergency-action levels (EALs) to classify accidents, but were limited to.' automatic sheltering of a 2-mile-zone and 5-mile' downwind sectors.
There is a need
!
for additional guidance'on protective action decisionmaking. - The NRC. inspector noted that EALs were being upgraded, in accordance.with written commitments, and that new guidance was being created to' aid SOSs in making efficient protective action recommendations (PARS).)
02.06 Ability to implement and recommend protective
!
actions (See 02.05 above.)
!
02.07 Understanding of relations between plant' status
and PARS (See 02.05 above.)
02.08 Ability to carry out notifications (The NRC inspector determined that key personnel interviewed
(see 02.05 above) were able to' effectively carry
out notifications.)
,
02.09 Training availability for offsite groups (The NRC inspector reviewed records and determined that training was made available to offsite support groups.)
j
!
Q
______ __ __ -
i
>.,. a.,
.
i
3.
Exit Interview The NRC inspector met with the NRC senior resident inspector and licensee representatives denoted in paragraph 1 on August 27, 1987, and summarized the scope and findings of the inspection as presented in this report.
The NRC inspector explained that all inspection procedures will be completed during the coming annual exercise.
_____ __- -- ____-__-__- - _-__ __
_
_