0CAN089005, Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001

Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001

ML20059D520
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/27/1990
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	Office of Nuclear Reactor Regulation
References
0CAN089005, CAN89005, IEB-89-001, IEB-89-1, NUDOCS 9009070072
Download: ML20059D520 (3)

Text

4 M r \- 1 s,

y

'# ," fhj h{g

=

Ent!rgy Operations,Inc.

Fbute 3, Ebx 137G -

@ 8t i1S Rescua AR 72001 -

Te 501-964 3100 I

1 1

I August 27, 1990 OCAN089005 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555 ATTN: Director,' Office of-Nuclear Reactor' Regulation-

Subject:

Arkansas Nuclear One - Units 1 & 2  ?

Docket Nos. 50-313 and 50-368'

' License Nos. DPR-51 and NPF-6 Use : ~ Inco:sel ti i Material For Steam Generator Repairs .

i Gentlemen:

In accordance with 10CFR50.55a(c)(3), Footnote 6, Entergy Operations requests authorization to use Inconel 690 (I-690)- tubing and bar stock' for steam generator repairs at Arkansas Nuclear-Ono, Units 1 and 2 (AN0-1&2). ,

This tubing is used by Babcock & Wilcox.(B&W) .or sleeves and by Combustion Engineering for tuoe plugs. Cabcock & Wilcox and Westinghouse use I-690 bar stock for tube plugs. Currently I-690 tubint and bar stock are approved for l use for Class 1 components conforming to the require:nents of ASME Section

l. III, Division 1 through Code Case N-474-1, Supplerrent 5. '

1 .

A recent tube plug failure in 11 orth Anna 1 reported in Builetin 89.01 and  :

the observation of cracked plugs in McGuire 2 (Notice 89-65) have high-' -i lighted the potential for stress corrosion cracking in Inconel 600 (I-600)  ;

in a primary coolant environment. To improve the performance of their i sleeves and plugs, vendors like B&W have-switched to matericls which are less susceptible tn stress corrosion cracking in the orimary coolant 1

environment. For the upcoming ANO-1 r?f ueling outage (IR9), B&W proposes to 4 utilize I-690 tubing material for sleeves to oe installed in the ANO-1 steam  ;

generators as a part of a preventive sleeving program and I-690 bar stock fcr any plugs which might be required.

An assessm9n;. of I-690 for steam generator sleeves and plugs in AN0-1&2 has l recently been performed. The focus of this evaluation was on the expected stress corrosion cracking behavior of I-690 as compared to I-600 when ,

exposed to high temperature water.

000C7 1

\ ,-

I l

e Sgg,qsga:ggsf PNU u

____ Y _ ._.

. , t

• c .

U. S. NRC Page 2 August 27, 1990 t

The assessment identified two studies in which the long term stress corrosion cracking data on reverse U-bends for I-690 in primary coolant (with hydrogen) were presented. These studies are presented in papers by

~

C. Grimond in."The Corrosion Performance of Alloy 690," and by T. Yonezawa, et al. in " Evaluation of the Corrosion Resistance of Alloy 690." These ,

papers were published in EPlil NP-46655-SR.

In Grimond's paper, Framatome-reported no cracking of I-690 af ter 12,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> in 680 F primary water, while mill annealed I-600 cracked in the same tests in 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

In Yonezawa's paper, data from long term tests on cold worked-.I-600 (mill annealed and mill anneal plus therelly treated) and cold worked I-690 tubing (mill annealed and mill anneal plus thermally treated) are reported for 680 F primary water. The mill annealed I-600 specimens began-failing after 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. No I-699 failures were reported after the total test.

duration of 12,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

The results of the assessment suggest an I-690 lifetime forty times longer than mill annealed I-600 and about twenty times longer than thermally ,

treated I-600. Therefore, from tht. literature, it appears that I-690 it the superior plug and sleeve material-due to its increased corrosion resistance for PWR service, and all available test data suggest i; will exceed a forty year design life.

This is not an emergency request; however, we would appreciate an. _ l expeditious review and approval of this request. This is nectssary to support our planned use of I-690 sleeves and plugs during 1R9 which is scheduled ;o begin on October 1, 1990.

We will change from using I-600 to I-690 sleeves by a.10CFR50.59 review I

after receiv'ng approval for use of I-690. This review will be based on qualifich i testing that is currently scheduled to be completed just prior to the con ..ncement of 1R9.

i If you have any questions, or require ar:ditional information, please contact I

my-office.

Very truly yours, sw .dMa James J. isicaro Manager, Licensing l

JJF:lw i

r

.. .? '  ;

U. S. NRC Page 3:  !

August 27, 1990

~

cc: Mr. Robert Martin i U. S. Nuclear Regulatory Commission l Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 >

NRC Senior Resident-Inspector o Arkansas Nuclear One - ANO-1 & 2 "

Number 1, Nuclear Plant Road-Russellville, AR 72801 Mr. Thomas W. Aic. vion L'RR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail-Stop 11-8-19 One White Flint Morth 11555 Rockville Pike Rockville, Maryland 20852' 1

Mr. Chester Poslusny NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-8-19 One White Flint North 11555 Rockville Pike m Rockville, Maryland 20852 Ms. Greta Sicus, Director Division of Radiation Control-and Emergency Management-Arkansas Department of Health 4815 West Markham Street ,

Little Rock, AR 72201 t

l

[

1 l

l l l 1