ML20207M925

Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl

ML20207M925
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/11/1999
From:	Nick Hilton NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9903190279
Download: ML20207M925 (26)

Text

- - . - . - ~ - - - . - . - - - . . . . _ , - - . - - . . . _ - _ - _ . - _ -

LICENSEE: Ent:rgy Operations, Inc. Mach 11, 1999 FACILITY: Arktnsas Nucis:r Ons, Unit 1 (ANO-1)

SUMMARY

OF MARCH 2,1999, MEETING WITH ENTERGY OPERATIONS, INC., REGARDING ARKANSAS NUCLEAR ONE, UNIT 1 STEAM GENERATOR INSPECTION AND REPAIR On March 2,1999, representatives of the Nuclear Regulatory Commission (NRC) and Entergy Operations, Inc. (Entergy, licensee), met to discuss Arkansas Nuclear One's (ANO's) steam generator inspection and repair plans for an upcoming Unit i refueling outage. The meeting was held at NRC Headquarters in Rockville, Maryland. A notice of this meeting was issued on February 17,1999. Enclosure 1 is a list of attendees. Enclosure 2 is the licensee's handout used at the meeting.

Entergy discussed its efforts to develop an alternate repair criteria to address steam generator tube corrosion resulting from intergranular attack (IGA). The approach would establish a maximum allowable accident leakage due to IGA, assign a leakage value to each flaw, then determine the number of flaws allowed to remain in service to meet the previously determined maximum allowab!e accident leakage. Entergy also briefly discussed repair criteria under development for tube end cracking and the steam generator tube re-roll repair method for both the upper and lower tubesheets. Finally, the licensee discussed its planned schedule for the submittal of the Technical Specification amendments necessary to support the steam generator inspection and repairs for the outage scheduled to begin in September 1999.

Due to the relatively short amount of time between Entergy's planned submittal and desired approval dates, the staff requested that Entergy prioritize the submittals.

ORIGINAL SIGNED BY: l Nicholas D. Hilton, Project Manager i Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation ,

Docket No. 50-313  !

Enclosures:

As stated (2) i cc w/encls: See next page i

] {P] g DISTRIBUTION:

HARD COPY E-MAIL Docket S. Collins /R. Zimmerman (SJC1/RPZ) J. Tsao (JCT)

PUBLIC J. Zwolinski(JAZ)/S. Black Chris Nolan (MCN)

PD4-1 RF J. Hannon (JNH) D. Lange (DJL)

N. Hilton P. Rush (PJR1) K. Brockman (KEB)

OGC C. Beardslee (CDB) L. Berry (LGB)

ACRS , , , ( C Ff>. Long (SML)  ;

)

~

l DOCUMENT NAME: G:\ANO1FINA\MTS0302.WPD [

To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with j attachment / enclosure N = No copy OFFICE PM/PD4-1 E LA/PD4-1_ E (A)D/PD4,-1 // -g l NAME N.Hilton [ L. Berry h G. Dick h DATE 03/d /99 03/ \ \ /99 03/ f l /99 9903190279 990311 PDR ADOCK 05000313 G PDR

L

, puenq y S UNITED STATES g

j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 2006H001 Q* *4***

/

March 11, 1999 l

LICENSEE: Entergy Operations, Inc.

FACILITY: Arkansas Nuclear One, Unit 1 (ANO-1)

SUMMARY

OF MARCH 2,1999, MEETING WITH ENTERGY OPERATIONS, INC., REGARDING ARKANSAS NUCLEAR ONE, UNIT 1 STEAM GENERATOR INSPECTION AND REPAIR I

I On March 2,1999, representatives of the Nuclear Regulatory Commission (NRC) and Entergy Operations, Inc. (Entergy, licensee), met to discuss Arkansas Nuclear One's (ANO's) steam generator inspection and repair plans for an upcoming Unit 1 refueling outage. The meeting was held at NRC Headquarters in Rockville, Maryland. A notice of tnis meeting was issued on February 17,1999. Enclosure 1 is a list of attendees. Enclosure 2 is the licensee's handout used at the meeting.

Entergy discussed its efforts to develop an attemate repair criteria to address steam generator tube corrosion resulting from intergranular attack (IGA). The approach would establish a maximum allowable accident leakage due to IGA, assign a leakage value to each flaw, then determine the number of flaws allowed to remain in service to meet the previously determined maximum allowable accident leakage. Entergy also briefly discussed repair criteria under development for tube end cracking and the steam generator tube re-roll repair method for both the upper and lower tubesheets. Finally, the licensee discussed its planned schedule for the submittal of the Technical Specification amendments necessary to support the steam generator inspection and repairs for the outage scheduled to begin in September 1999.

Due to the relatively short amount of time between Entergy's planned submittal and desired approval dates, the staff requested that Entergy prioritize the submittals.

Nicholas D. Hilton, Project Manager Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosures:

As stated (2) cc w/encis: See next page

Entergy Operations, Inc. Arkansas Nuclear One, Unit 1 cc:

Executive Vice President Vice President, Operations Support

& Chief Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Director, Division of Radiation Wise, Carter, Child & Caraway Control and Emergency Management P. O. Box 651 Arkansas Department of Health Jackson, MS 39205 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Mr. C. Randy Hutchinson Vice President Operations, ANO Entergy Operatons, loc.

Winston & Strawn 1448 S. R. 3?3 1400 L Street, N.W. Russellville, AR 72801 Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County, Pope County Courthouse Russellville, AR 72801

March 2,1999 Meeting between Entergy Operations, Inc.

and Nuclear Regulatory Commission ATTENDANCE LIST Name Affiliation Phillip Rush NRC/NRR John Tsao NRC/NRR Cheryl Beardslee NRC/NRR Steve Long NRC/NRR Nick Hilton NRC/NRR Mark Smith Entergy Dale James Entergy John Hathcote Entergy Steve Bennett Entergy Jeff Brown Framatome Tech.

Sid Powell Florida Power Corp.

Patrick Peterson Florida Power Corp.

Tony Petrowsky Florida Power Corp.

Dan Mayes Duke Enclosure 1

\~

~

o

d!!h

=gggy ~ . . . . _

j .

k t

i-AXO-1 OTSG Upper Tubesheet IGA Alternate Repair Criteria i

March 2,1999 t

s-2 2

m ANO-1 UpperTubesheet ARC i

4 e

= Entergy

~ ~ . . _

Purpose of Meeting gg

! + IGA Alternate Repair Criteria

+ TEC-ARC / Re-roll Summary

+ Timing and Scope i

ANO-l UpperTubesheet ARC

.  ! .Ii !  ;:jI! !lll;Ill,ll., i f l !

i1!l!

"4

/

1 l 7 i

a sni ce t

e 4 -

t e 2 e h b

s e

i t

on as cn r

e Z

e n

o D

u n *5 -

T id I o7 r

e nin p

i a is2 u _

ht

• U p 0m 3

4 R e l

c x

i t e ,

3 E

y e _

whs l / _

o f .

Ge i

< y Sb -

T Tb u~ id s

n o

s nd oe O

t it ir g aie cf aa n i i icp c dn t

d e r d a I n de I nR e l C 0I 8

5l 2

l A

p' 4 p .

U' #

C R

A t

y -

e e

g-

~

h s

e r ..

b u

t.

e..

f, f

. , w x* ~ T

• T 31 M

';? d!.'! r

?

- e

n. .

- - p p

E- 1 ' ,,

esI -

i ) '-

~

U

! i ,

1

@ O N

A

m -

==

Entergy ANCi-1 OTSG IGA History ,

Ell c

+ Inservice Since Late 70's

. Sulfurintrusion

. Three dimensional (volumetric) corresion at the grain bountaries

. Small volumetric patches - non crack like

+ Dispositioned Several Different Ways

. Signal-to-Noise (pre IR10)

. Depth sizing using bobbin (pre IR13)

. Multi-parameter linear regressior depth sizing (IR13)

. One cycle ARC based on in-situ pressure testing (IR14)

ANO-1 UpperTubesheet ARC

P a

7Entergy

~ . - -

ANO-1 OTSG IGA History gg,

+ No Leakage Observed sv # '*"

. Includes a May 1996 plant transient (2100 psid)

. 1 R14 Bubble Test

., Lab and in-situ pressure / load testing

+ No Growth

, Chemical analysis from IR13 pulled tubes indicate a bemgn environment

. Bobbin amplitude comparison 1RI1 to 1R13 i

. Zero average change from 1R13 to 1R14 i

ANO-l UpperTubesteet ARC

e.

e

~~ Entergy 1

~ .... _

Bobbin Amplitude Comparison

~

lh, "A" OTSG Amplitude Change From Corrected 1R13 HF Bobbin to 1R14 MR Bobbm 60 . .

30 .

40 .

N c

$30..

E 20 10 . ,

i 0  :  :  :  : :5:  :  :  :  :  :  :  :  :  : :E;  : , :

i  ;;;;;;;ya aa  :  : :  :  : :

Voltage Change ANO-l UpperTubesheet ARC

g ,'.

W __gy Enter ANO-1 Used in 4 i March 1998 (1R14) l

• '.f

~

e .

e J .

t

+ BWOG Project

. Voltage based approach i . Partial submittal Aug.1997 i t

. Difficulty developing a correlation between leakage probability and amplitude

. Flaws would not leak

. Informed the NRC that the voltage based approach was no longer being pursued

+ Statistical Based Approach

. Coupled with in-situ pressure testing

. Tested 40 IGA patches

! ANO-1 Upper Tubesheet ARC

., .i j .

m m

5Entergy .-

Approach used m.

March 1998 (1R14) '

~ .

1:

+ Used a 95% Confidence Level for Leakage

. Postulated accident leakage limit of Igpm

.. Considering other modes of degradation selected 0.5 gpm

. Modeled a 0.3" long crack and calculated leakage

. This determined number of flaws required for in-situ testing

+ ECT Inspection

. Used Bobbin 400/200 mix for detection

. Plus-point /RPC for characterization

. Length and width sized using 0.115" pancake

. Growth Rate Comparison ANO-1 UpperTubesheet ARC

= Entergy

~ . . . -

Extent Sizing Comparison Fractography vs 0.115" Pancake for Axial Extent 1

0.9 08 ,

0.7 06 5 + +

05 *

• b ,

$$ a 1R13 Tube Pull Data ci 04 ++

+ ++

+ ,** ,

0.3 , +

4 e2 0.1 0 . . . . - > - ' '

OO 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 DE Length ANO-1 Upper Tubesheet ARC D*#pt g

I

..l:

e

= Entergy

~ . . . . _

Scatter Plot of LxW 1

IGA Flaw Ar6a (L x W) as Measured by 0.115" Pancake No Leakage Observed 1

~-~

, Existing IGA X . in-situ IGA 0.8 - ~ ~ ~ ~ ~ ~ - . _ .

X' X Lab Data-TS 0.7 _ _ . - _ _ .

+ 1R13 Tube X X ps 7 A EDM Holes

• 0.6 E X X X X

f0.5 XX 3 + X

+X 3 0.4 ._g___ M . X I. _ y __ __. _ __

4 XX

• X ,.

0.3 , .g g _

x, X. X *

• I t M ,

02 gt f YJ

• yl$,d 0.1 ,, ++, -,_.

0

, 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 ANO-1 UpperTubesheet ARC cire s w ince )

y

.l s=se Entergy

~ . . . . . . -

Scatter Plot of Volts vs Length

~

$ i B

. +

0.115" Pancake Axial Length vs Bobbin Amplitude No Leakage Observed 3.5 3 '

X 25 -

e i e = l

$ 2 .._ .x . . _ - . . ._ _ . _ . .

i . in-situ IGA i

J X X Lab Data-TS

5 .. .x _X/ x x x i a X i a

i t se t,**.* .__ _ . y - .x x_x_..x_ _ . . .

. + ++ X X 0~5 ~

• ~~ ~

" 8.4

. ~+{#~~ *x x x 0 ., .. -

x* x .

) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

ANO-1 UpperTubesheet ARC Axial Exw (incM

Allt i Entergy

~ . . . . . -  ;

Approach for 1R15 .

f .

ll 3

+ Evaluated Two Different Options j . Depth sizing

. Statistica!

+ Multi Parameter Linear Regression

. Used lab data and pulled tube data

. Poor correlation coefficient and RMSE Depth Sizing

+ Exploratory Research

, . Looked at other ECT parameter combinations

. Bobbin /plus-point /0.115" pancake '

. Up to a combination of 14 variables

. Plus-point provides the best fit (CC of 0.52) l ANO-l UpperTubesheet ARC

._. i s

a m

= Enter- gy Plan for 1R15 ARC gg

+ Statistical Basis 1

+ Build from 1R14 work

+ Confirm No Growth

. Bobbin used in past

. Plus-point provides a better comparison to depth i

ANO-1 Upper Tubesheet ARC

m a

1 s=s=

i, -.niergy Bobbin Volts vs Depth i

MR Bobbin Voltage As a Function of Maximum %TW t

2.5 l

o Lab Samples a Tube Pull 2 o. . _ _ _ ._

o i O

1.5 -. _ ____ . . _ . a_. . _ _ . _ _ _ _ __.

o oo o

..0 g o ,

1

. _3 o

I " 0

o. '

. _ . _ . m

• i i

o o  ;

o" o '

o o 5 0 o c * * '

S o o E o

0.5 , _. o . _ , . . . .

j O o o 5 o B '

• o o o o o l o o 6 8 o o

0 , ,. . . _ , _ _ _ , _.

____4 _ . _

___~ ._ _ _ _ _ , ,

0% 10 % 20% 30 % 40% 50 % 60% 70 % 80% 90 % 100 %

"*d"""*'* "

ANO-1 UpperTubesheet ARC t

G b 96

~=~~ .Entergy

! Plus-Point Volts vs Depth i

P s' . l

, . g- .

- 2 l Plus-Point Voltage As a Function of Maximum %TW j I

! O Lab Date l 4.5 m Tube Pull a 1

4 - -

3.5 . - . .- ._.

?

g 3 . ._ . _ _ _ _ . . _ _ . _ _ _

~a O

> 2.5 0 4

-e 2 - - - E - . _ .

I l 1.5 9 o a g ,

O o e

I - ' - ~ ~ ~ '

O'o' g O OO O O o

U.5 o 0 0

$en --

0 o O O 00gO< > og o , , _ _ , _ .

.. __ . _ . _ , __________y____. . , . _ . . _ _ _ _ ._ _,. _ ,

0% 10% 20 % 30% 40*/. 50 % 60 % 70% 80 % 90 % 100 %

ANO-l UpperTubesheet ARC

m i

• Entergy

~

i

~. _ g Approach for 1R15

-v.n.~-,,..- - .

g , , : g'

[

+ 100% Bobbin Exam (400/200 mix)  :

+ Plus-Point /RPC for Confirmation and .

Characterization ,

. L x W Extent Sizing with 0.115" Pancake

. Amplitude from Plus-Point >

l

+ Confirm no Change in Volts using Plus-Point or -

~

Bobbin '

+ Apply Hypergeometric Sampling

+ Iteral:ive Process ANO-1 UpperTubesheet ARC

=h-- 4 664 ep - _,g

^^# *- " "

me M = W*** * * * '

..1-e s

~~ Entergy -

Approach for 1R15

~

lll

+ Establish Allowable Accident Leakage (e.g. 0.3 gpnt

+ Sort Axial Extents of the IGA Patches

. Assign a Leakage Value to Each Flaw

. Determine Number of Flaws to Meet Accident Leakage

+ Determine Population Size

. Including in-situ data from 1R14

+ Use Hypergeometric Approach and Determine if Additional In-situ is Required 4

ANO-1 UpperTubesheet ARC

j 4

A m

=

[e}f ~~

Example o (a Cd )x(b C c-di1

.I a+b Ce I

l l

Defined Allowable Leakrate (0.3 GPM) l

• a = Number ofleaking patches that sum to 0.3gpm (25)

• b = Number of non-leaking patches (300) e d = Number of patches leaking during in-situ (0) l

• P = Probability of finding a leaking patch in sample sizeif there existsa or more l leaking patches (95%)

l

• e = Required number of patches to be tested - 31 i

l ANO-1 UpperTubesheet ARC

m m

fi

== Enter gy __- ,

Summary

. lll

+ Volumetric IGA Inservice Since Late 70's

, + Not Growing

+ Not a Structural Concern

+ Postulated Accident Specifically Addressed

+ Confirm No Growth Using Amplitude

. Repair IGA that exceeds a specific amplitude change

+ Possible In-Situ Based on Statistical Model 4

ANO-1 Upper Tubesheet ARC

em 'l

• Entergy Summary of TEC ARC F6 -

. . Elll

+ Identified During 1R14 (March 1998) l

+ No Structural Concern

+ Leakage is Addressed

. TS Bow / Hole Dilation

+ Limit tt Axial Flaws

\ x Outside Repair IGA that exceeds a specific amplitude change N, ossible In-Situ Based on Statistical Model S

ANO-1 Upper Tubesheet ARC

._._..._.___._____m.__ . .__ ._____ _ _ _ ___._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _

9

==

Entergy Summary of Re-roll  :

. HII

+ BWOG Project

+ TS's Currently Allow one Re-roll (UTS only)

+ Re-rollIntroduces Non Stress Relieved Joini

+ EPRI GL's Require a Sample Inspection in the LTS

+ Resolving Axial Tube Loading Issues

+ Incorporate Into Topical ANO-1 Upper Tubesheet ARC 1 -

l & *b

=

Entergy Schedule gg

+ OD IGA - Submittal Targeted for April 1999 'i

. Correlation and depth sizing unsuccessful l . Proposed approach similar to cycle 15

+ TEC - Submittal Targeted for April 1999

. Issue described in IN 98-27

+ Re-roll Optimization - Submittal Targeted for May 1999

. Proposed approach similar to cycle 15 l

. Addresses PSC on l + Next Outage Begins September 1999 ANO-1 Upper Tubesheet ARC

.