IR 05000313/1987004
| ML20215M512 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/11/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Campbell G ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8705130286 | |
| Download: ML20215M512 (1) | |
Text
3 h
MAf I-l 196T In Reply Refer To:
Dockets:
50-313/87-04-50-368/87-04
^rkansas Power & Light Company ATTN:
Mr. Gene Campbell Vice President, Nuclear Operations-P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
Thank you for your letter of April 13, 1987, in response to our letter and NRC Inspection Report 50-313/87-04; 50-368/87-04 dated March 6, 1987. We have reviewed your reply and find it responsive to our concerns. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
Sincerely, ORIGINAL SIGNED BY:
J. E. Gagliardo, Chief Reactor Projects Branch cc:
J.>M.
Levine, Director Site. Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director bec to DMB (IE35)
bec distrib. by RIV:
RPB Resident Inspector R. D. Martin, RA R&SPB Section Chief (RPB/B)
D. Weiss, RM/ALF RIV File DRSP RSB MIS SYSTEM RSTS Operator Inspector Section Chief W. L. Fisher R. L. Bangart R. E. Hall Project Inspector, RPB D. B. Matthews, NRR
\\
V:EP C:EP& ),
C:R&SPB $
C-C:RPB Yan WLFisher D
ter JEGagli o
Jt Lp/\\ /87 5/"]/87
/S7 6 /in/
0/87 u
/
8705130286 870511 PDR ADOCK 05000313 g
{
G PDR t
L
.
,
,
.
..
ARKANSAS POWER & LIGr4T COMPANY POST OFFICE box 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000
^ P "" '
7 73@ Egg
- [s 1
'
0,!-
OCAN048704 f
APR I 61987 u
U. S. Nuclear Regulatory Commission
_ d__, _ _
Region IV 611 Ryan Plaza Drive, Suite 1000
-
- -
__
_ _.
Arlington, TX 76011 ATTN: Mr. Robert D. Martin Regional Administrator SUBJECT: Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Emergency Preparedness Inspection 87-04
.
Gentlemen:
-
-
' ~
The Arkansas Power and Light Company (AP&L) is in receipt of your correspondence of March 6, 1987 (SCNAD38701) concerning the routine, unannounced inspection conducted by Mr. Nemen Terc during the dates of January 11-16, 1987.
During this inspection, one emergency preparedness deficiency
,
l (313-368/8704-01) was identified based upon the following five (5) findings:
,
1.
The Unit 1 Abnormal Operating Procedure A0P-1203.19, "High Activity in the Reactor Coolant," does not include a follow-up action requirement for sampling the primary coolant. This is necessary to evaluate actions according to Technical Specification requirements.
l<
l 2.
The EPIPs do not contain a flow diagram equivalent to that of IE Information Notice No. 83-28 dated May 4, 1983. As a consequence, the teams interviewed did not consider evacuation before a release had occurred during General Emergency conditions with extensive fuel damage l
and large amounts of radioactivity in the containment.
!
l 3.
There is no direct correlation between the example initiating I
conditions of NUREG 0654, Appendix I, and the EALs found in the Plan.
l In a few cases, it was shown that the departure from NUREG 0654 is in a nonconservative direction. For example, no EALs based upon installed
instrumentation are listed in the Plan that correspond to a severe loss
!
l of fuel cladding.
l
'
4.
EALs in the Plan are not always equivalent to those in NUREG 0654 in promptness of notification or in establishing the severity of the emergency class.
NN N b h5 pg
i m
~. e=1-ur,ume
.reo
-
.
.
=
-
,
.
-2-April 13, 1987 t
5.
Form 1904.02A, " Emergency Class /Offsite Dose Projection Worksheet,"
does not provide for computing an integrated dose based upon expected release duration and projected dose rate.
Item (1) has been addressed by revising the Unit 1 Abnormal Operating
~
Proceduro A0P-1203.19 "High Activity in the Reactor Coolant" to include the requirement for primary coolant sampling as part of follow-up ' action. This revision was effective as of March 5, 1987.
Item (5) will be addressed by developing and implementing a revision to procedure 1904.02, Form 1904.02A " Emergency Class /0ffsite Dose Projection Worksheet" to record the necessary information to calculate a projected total dose. This total dose value can then be compared to protective action
-
guides to arrive at a protective action recomendation. This procedure change will be incorporated by May 31, 1987.
Items (2), (3), and (4) relating to the methodology of Inspection and Enforcement (I&E) Information Notice 83-28 and the correlation of the AN0 Emergency Action Levels (EAL) to those listed in NUREG 0654, Appendix I will be approached in two (2) phases.
Phase I will be to reexamine our EAL structure with emphasis on addressing
' incorporation of the intent of the I&E Information Notice 83-28 methodology
-
and to identify where, if possible, EALs could be based upon installed
-
instrumentation. This effort will also include a review of current industry
..
activity in this area to determine if an approach applicable to the ANO case has been developed elsewhere.
The end product of Phase I will be to determine what action can be taken to address the concerns identified in the January,1987 inspection. Once these actions are identified, a schedule for implementation will be developed and Phase II of the effort will be to implement the identified changes in accordance with that schedule. Phase I is currently scheduled to be completed by June 30, 1987.
.
If you have any questions regarding this item, please contact my office.
Very truly yours,
<
M
. Ted Enos, fianager Nuclear Engineering and Licensing JTE:MT:lw
.
. _ - _ -
. _ _.