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{{#Wiki_filter:Arkansas Power & UgM Company O                                                                  f$'Lc,,apw
{{#Wiki_filter:Arkansas Power & UgM Company O                                                                  f$'Lc,,apw
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           .                                                                    tm Rn AR UM Tel f,01377 t.(03 t
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October 19, 1989 BCAN198914 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
October 19, 1989 BCAN198914 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555


==Subject:==
==Subject:==
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NaF-6 Response to NRC Bulletin 87-01
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NaF-6 Response to NRC Bulletin 87-01 Additional Information Gentlemen:
  ,
By letter dated September 25,1987(SCAN 998712), Arkansas Power & Light Company responded to NRC Bulletin 87-01, " Thinning of Pipe Walls in Nuclear Power Plants." In that correspondence we discussed our plans for developing an inspect:on program for secondary pipe wall thinning. At this time AP&L wishes to make you aware of the status of and the changes in that program.
Additional Information Gentlemen:
By letter dated September 25,1987(SCAN 998712), Arkansas Power & Light Company responded to NRC Bulletin 87-01, " Thinning of Pipe Walls in Nuclear
  ,
Power Plants." In that correspondence we discussed our plans for developing
  '
an inspect:on program for secondary pipe wall thinning. At this time AP&L wishes to make you aware of the status of and the changes in that program.
AP&L now has a complete Secondary Pipe Wall Thinning Program Procedure 1092.090, Rev. 2, approved August 17, 1989. It provides directions for choosing inspection locations and for determining inspection frequencies.
AP&L now has a complete Secondary Pipe Wall Thinning Program Procedure 1092.090, Rev. 2, approved August 17, 1989. It provides directions for choosing inspection locations and for determining inspection frequencies.
The current method for determining inspection frecuencies, which is being utilized in the current ANO-2 refueling outage anc will be utilized in future outages, replaces the inspection schedule comitted in our September 1987 correspondence. The determination of inspection frequencies on plant
The current method for determining inspection frecuencies, which is being utilized in the current ANO-2 refueling outage anc will be utilized in future outages, replaces the inspection schedule comitted in our September 1987 correspondence. The determination of inspection frequencies on plant piping components is now established at appropriate scheduled 'utages utilizing field inspection results and wear rates based on those results, rather than basing inspections strictly on generic type guidelines and system design characteristics. This approach is consistent with NilMARC/EPRI guidelines (e.g., Appendix A to NUREG-1344).
    '
piping components is now established at appropriate scheduled 'utages utilizing field inspection results and wear rates based on those results, rather than basing inspections strictly on generic type guidelines and system design characteristics. This approach is consistent with NilMARC/EPRI guidelines (e.g., Appendix A to NUREG-1344).
                                                                                                            !
                                            '
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8910250365 891o19 gDR    ADOCK0500g3 e t p
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     > .. - .g.                                                                                                            t
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                 . U. S. NRC.
                 . U. S. NRC.
Page 2                                                                                                l October.19, 1989                                                                                      l
Page 2                                                                                                l October.19, 1989                                                                                      l L                                                                                                                        i l
  > :,.                                                                                                                    :
The categorization of inspection areas delineated in our 1987 correspondence                        ,
                                                                                                                          ,
L                                                                                                                        i
  !'
                                                  ,                            .
l The categorization of inspection areas delineated in our 1987 correspondence                        ,
F                  was developed using the EPRI guidelines. Those guidelines are now a part of                          !
F                  was developed using the EPRI guidelines. Those guidelines are now a part of                          !
b                  the EPRI computer codes, CHEC and CHECMATE, that the secondary Pipe Wall                            t Thinning Inspection Coordinator currently utilizes in determining inspection
b                  the EPRI computer codes, CHEC and CHECMATE, that the secondary Pipe Wall                            t Thinning Inspection Coordinator currently utilizes in determining inspection
Line 65: Line 40:
If you have any questions, please do not hesitate to contact me.                                    ;
If you have any questions, please do not hesitate to contact me.                                    ;
                     '!rry 5..'uly yours ,
                     '!rry 5..'uly yours ,
                                ''
                                    '
                                       . d&
                                       . d&
James        . Fisicaro                                                                          !
James        . Fisicaro                                                                          !
Manager, Licensing                                                                                  j JJF/RP/1w                                                                                            !
Manager, Licensing                                                                                  j JJF/RP/1w                                                                                            !
cc:                            Mr. Robert Martin U. S. Nuclear Regulatory Comniission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arke.nsas Nuclear One - ANO-1&2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck NRR Project Manager, Region IV/ANO-1
cc:                            Mr. Robert Martin U. S. Nuclear Regulatory Comniission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arke.nsas Nuclear One - ANO-1&2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Poslusny l                                                    NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 1'                                                  One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 l
  '
l 4
U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Poslusny l                                                    NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission
m -          ,  ,-  -,          .,}}
.
NRR Mail Stop 13-D-18 1'                                                  One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 l
l
          .
4 m -          ,  ,-  -,          .,}}

Latest revision as of 00:39, 1 February 2020

Submits Addl Info to Util 870925 Response to NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. Secondary Pipe Wall Thinning Program Procedure 1092.090,Rev 2,approved on 890817
ML19325D707
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 10/19/1989
From: James Fisicaro
ARKANSAS POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0CAN108914, CAN108914, IEB-87-001, IEB-87-1, NUDOCS 8910250365
Download: ML19325D707 (2)
v • d • e


Text

Arkansas Power & UgM Company O f$'Lc,,apw

. tm Rn AR UM Tel f,01377 t.(03 t

October 19, 1989 BCAN198914 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NaF-6 Response to NRC Bulletin 87-01 Additional Information Gentlemen:

By letter dated September 25,1987(SCAN 998712), Arkansas Power & Light Company responded to NRC Bulletin 87-01, " Thinning of Pipe Walls in Nuclear Power Plants." In that correspondence we discussed our plans for developing an inspect:on program for secondary pipe wall thinning. At this time AP&L wishes to make you aware of the status of and the changes in that program.

AP&L now has a complete Secondary Pipe Wall Thinning Program Procedure 1092.090, Rev. 2, approved August 17, 1989. It provides directions for choosing inspection locations and for determining inspection frequencies.

The current method for determining inspection frecuencies, which is being utilized in the current ANO-2 refueling outage anc will be utilized in future outages, replaces the inspection schedule comitted in our September 1987 correspondence. The determination of inspection frequencies on plant piping components is now established at appropriate scheduled 'utages utilizing field inspection results and wear rates based on those results, rather than basing inspections strictly on generic type guidelines and system design characteristics. This approach is consistent with NilMARC/EPRI guidelines (e.g., Appendix A to NUREG-1344).

8910250365 891o19 gDR ADOCK0500g3 e t p

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,6'

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. U. S. NRC.

Page 2 l October.19, 1989 l L i l

The categorization of inspection areas delineated in our 1987 correspondence ,

F was developed using the EPRI guidelines. Those guidelines are now a part of  !

b the EPRI computer codes, CHEC and CHECMATE, that the secondary Pipe Wall t Thinning Inspection Coordinator currently utilizes in determining inspection

t. locations.  !.

If you have any questions, please do not hesitate to contact me.  ;

'!rry 5..'uly yours ,

. d&

James . Fisicaro  !

Manager, Licensing j JJF/RP/1w  !

cc: Mr. Robert Martin U. S. Nuclear Regulatory Comniission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arke.nsas Nuclear One - ANO-1&2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Poslusny l NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 1' One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 l

l 4

m - , ,- -, .,

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