ML20237C700: Difference between revisions

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ARKANSAS POWER & LIGHT COMFANY POST OfflCE DOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 i   $@ SON $b 0,,~~
ARKANSAS POWER & LIGHT COMFANY POST OfflCE DOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 i
OCAN068710 U. S. Nuclear Regulatory Commission                                       Jtt 61987           !
$@ SON $b OCAN068710 0,,~~
Region IV                                                                                       p 611 Ryan Plaza Drive, Suite 1000                                     -
U. S. Nuclear Regulatory Commission Jtt 61987 Region IV 611 Ryan Plaza Drive, Suite 1000 p
Arlington, TX 76011 ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch
Arlington, TX 76011 ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch


==SUBJECT:==
==SUBJECT:==
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368                                               '
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Inspection Report Finding 313-368/8606-01
License Nos. DPR-51 and NPF-6 Inspection Report Finding                                                   ,
313-368/8606-01                                                             !


==Dear Mr. Gagliardo:==
==Dear Mr. Gagliardo:==
 
In our response dated August 1, 1986 (OCAN088606) to the subject inspection report finding, AF&L indicated thst certain modifications would be made to the CA1 and CA2 portals to enhance access control.
In our response dated August 1, 1986 (OCAN088606) to the subject inspection report finding, AF&L indicated thst certain modifications would be made to the CA1 and CA2 portals to enhance access control. The upgrades were described in our respense. Also, the compensatory measures to be taken in the interim were described in our letter of December 19,1986(OCAN128668).
The upgrades were described in our respense. Also, the compensatory measures to be taken in the interim were described in our letter of December 19,1986(OCAN128668).
Subsequent evaluations have shown that our previous. described modification would not provide the level of access control deemed necessar/ by AP&L management. Therefore, AP&L has revised the scope of the inodification as described in the attached CA1 and CA2 modifications. The revised modification will require additional time for implementation. Considering additional engineering and equipment delivery times, the modifications are currently scheduled to be completed by January 31, 1988. In the interim, the compensatory measures described in our {{letter dated|date=December 19, 1986|text=December 19, 1986 letter}} will be in effect.
Subsequent evaluations have shown that our previous. described modification would not provide the level of access control deemed necessar/ by AP&L management. Therefore, AP&L has revised the scope of the inodification as described in the attached CA1 and CA2 modifications.
The revised modification will require additional time for implementation. Considering additional engineering and equipment delivery times, the modifications are currently scheduled to be completed by January 31, 1988.
In the interim, the compensatory measures described in our {{letter dated|date=December 19, 1986|text=December 19, 1986 letter}} will be in effect.
The attached material contains safeguards information as defined by 10CFR73.21 and therefore should be handled appropriately.
The attached material contains safeguards information as defined by 10CFR73.21 and therefore should be handled appropriately.
Very truly yours,
Very truly yours,
                                                              . Ted Enos, Manager Nuclear Engineering and Licensing JTE:DEJ:lw ENCLOSUREENCLOSURE Attachment CONTAINS CONTAINS SAFEGUARDS INFORMATIONSAFEGUARDS INFORMATL -
. Ted Enos, Manager Nuclear Engineering and Licensing JTE:DEJ:lw ENCLOSURE CONTAINS ENCLOSURE CONTAINS SAFEGUARDS INFORMATIONSAFEGUARDS INFORMATL -
UPON SEPARATION UPON                    THISSEPARATION THIS PAGE IS DECONTROLLED                 PAGE IS DECONTROLLED 8712220083 871214                                                                                             3 PDR ADOCK0500gi,3 m                                 _ _ _          ~ - - ' ~ _}}
Attachment UPON SEPARATION THIS PAGE IS DECONTROLLED UPON SEPARATION THIS PAGE IS DECONTROLLED 3
8712220083 871214 PDR ADOCK0500gi,3 m
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Latest revision as of 08:09, 2 December 2024

Forwards Revised Description of Mod of CA1 & CA2 Portals for Enhancement of Access Control,Described in 860801 Response to Insp Repts 50-313/86-06 & 50-368/86-06.Mods Scheduled to Be Completed by 880131.Encl Withheld (Ref 10CFR73.21)
ML20237C700
Person / Time
Site: Arkansas Nuclear  
Issue date: 06/30/1987
From: Enos J
ARKANSAS POWER & LIGHT CO.
To: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20237C696 List:
References
0CAN06871O, CAN6871O, NUDOCS 8712220083
Download: ML20237C700 (1)


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ARKANSAS POWER & LIGHT COMFANY POST OfflCE DOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 i

$@ SON $b OCAN068710 0,,~~

U. S. Nuclear Regulatory Commission Jtt 61987 Region IV 611 Ryan Plaza Drive, Suite 1000 p

Arlington, TX 76011 ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch

SUBJECT:

Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Inspection Report Finding 313-368/8606-01

Dear Mr. Gagliardo:

In our response dated August 1, 1986 (OCAN088606) to the subject inspection report finding, AF&L indicated thst certain modifications would be made to the CA1 and CA2 portals to enhance access control.

The upgrades were described in our respense. Also, the compensatory measures to be taken in the interim were described in our letter of December 19,1986(OCAN128668).

Subsequent evaluations have shown that our previous. described modification would not provide the level of access control deemed necessar/ by AP&L management. Therefore, AP&L has revised the scope of the inodification as described in the attached CA1 and CA2 modifications.

The revised modification will require additional time for implementation. Considering additional engineering and equipment delivery times, the modifications are currently scheduled to be completed by January 31, 1988.

In the interim, the compensatory measures described in our December 19, 1986 letter will be in effect.

The attached material contains safeguards information as defined by 10CFR73.21 and therefore should be handled appropriately.

Very truly yours,

. Ted Enos, Manager Nuclear Engineering and Licensing JTE:DEJ:lw ENCLOSURE CONTAINS ENCLOSURE CONTAINS SAFEGUARDS INFORMATIONSAFEGUARDS INFORMATL -

Attachment UPON SEPARATION THIS PAGE IS DECONTROLLED UPON SEPARATION THIS PAGE IS DECONTROLLED 3

8712220083 871214 PDR ADOCK0500gi,3 m

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