ML082490575

July 2008 Evidentiary Hearing - Applicant Exhibit E2-27-VY, Calculation VY-19Q-303r0

ML082490575
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/30/2008
From:	Herrmann T, Stevens G Structural Integrity Associates
To:	NRC/SECY/RAS
SECY RAS
References
06-849-03-LR, 10163217, 50-271-LR, Entergy-Applicant-E2-27-VY, RAS M-290 VY-19Q-303, Rev 0
Download: ML082490575 (7)

Text

PrcsH - --)-o Strctural Integrity Associates, Inc. File No.: VY-19Q-303 CALCULATION PACKAGE Project No.: VY-19Q PROJECT NAME:

Provide VY Support for Questions Related to Environmental Fatigue Analyses CONTRACT NO.:

10163217 CLIENT:

PLANT:

Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station CALCULATION TITLE:

Feedwater Nozzle Environmental Fatigue Evaluation Document Affected Project Manager Preparer(s) &

Domevont Pafed Revision Description Approval

, Checker(s)

Revision Pages Signature & Date Signatures & Date 0

1 - 7 Initial issue.

Terry J. Herrmann Gary L. Stevens 01/30/2008 01/30/2008 Terry J. Herrmann 01/30/2008 U.S. NULA REGU*LATORY COMM SION In the Miler Of___

6_

DOdkSt NO.

';-2 1

-Oficial Exhibit No. E2'2 OFFERED by plicant/Li :enseJtervetior NRIC Staff Other-IDENT D on '

17-11 Witness/Panel

-C

?Z Action Taken:

m REJECTED WITHDRAWN DrCKETED Reporter/Clerk USNRC August 12, 2008 (11:00am)

L(-

OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Page 1 of 7

ýF0306-01 RO

Structural Integrity Associates, Inc.

Table of Contents 1.0 INTRODU CTION...........................................................................................................................

3 2.0 A PPROACH.........................................................................................

3......................

....... 3 3.0 M ETHODOLOGY........................................................................................................................ 4 4.0 CALCULATION S.........................................................................................................................

5 5.0 CON CLU SION S........................

5 6.0 REFEREN CES..........................................................................................

..................................... 6 List of Tables Table 1: EAF Calculations for the Feedw ater N ozzle Com er...................................

......................... 7 File No.: VY-19Q-303 Revision: 0 Page 2 of 7 F0306-OI RO

Structural Integrity Associates, Inc.

1.0 INTRODUCTION

The purpose of this calculation is to perform a plant-specific evaluation of reactor water environmental effects for the reactor pressure vessel (RPV) feedwater nozzle identified in NUREG/CR-6260 [1] for the older vintage General Electric (GE) plant for the Vermont Yankee Nuclear Power Station (VY).

2.0 APPROACH Per Chapter X, "Time-Limited Aging Analyses Evaluation of Aging Management Programs Under, 10 CFR 54.21 (c)(1)(iii),"Section X.Ml, "Metal Fatigue of Reactor Coolant Pressure Boundary," of the Generic Aging Lessons Learned (GALL) Report [2], detailed, vintage-specific, fatigue calculations are required for plants applying for license renewal for the locations identified for the appropriate vintage plant in NUREG/CR-6260.

In this calculation, detailed environmentally assisted fatigue (EAF) calculations are performed for VY for one of the locations associated with the older vintage GE plant in NUREG/CR-6260. The older-vintage GE plant is the appropriate comparison to VY since the original piping design at VY was in accordance with USASB31.1 [3], as well as the fact that the older-vintage boiling water reactor (BWR) in NUREG/CR-6260 was a BWR-4 plant, which is the same as VY.

Entergy performed an initial assessment of EAF effects for VY in their License Renewal Application (LRA) that was submitted to the NRC in January 2006: Table 4.3-3 of the VY LRA provides the results of those evaluations. All but two of the VY locations evaluated for EAF in the LRA did not yield acceptable results for 60 years of operation, as they were based on generic analysis results from NUREG/CR-6260 that were not VY-specific. Plant-specific analyses have been recently completed to address those components for VY. Relevant chemistry input for this calculation is contained in Reference [5]. This calculation documents the EAF evaluation for the feedwater nozzle locations.

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Structural Integrity Associates, Inc.

3.0 METHODOLOGY Per Section X.M1 of the GALL Report [2], the EAF evaluation must use the appropriate Fen relationships from NUREG/CR-6583 [4] (for carbon/low alloy steels), which are the materials under consideration for the feedwater nozzle. Per Figure 2 and Table 2 of Reference [6], the two locations being evaluated are the feedwater nozzle safe end (carbon steel) and the feedwater nozzle forging comer (low alloy steel). Based on the materials of these locations, the appropriate expressions are:

For Carbon Steel [4, p. 69]:

Fen = exp (0.585 - 0.00124T' - 0.101S*T*O* 8*)

(1)

Substituting T' = 25'C in the above expression, as required by NUREG/CR-6583 to relate room temperature air data to service temperature data in water [7], the following is obtained:

Fen exp (0.585 - 0.00124(25°C)- 0.101S* T* O*e*)

(2)

= exp (0.554 - 0.101 S* T* 0* 0*)

)(3)

For Low Alloy Steel [4, p. 69]:

Fen = exp (0.929 - 0.00124T' - 0.101S*T*O* 8l*)

(4)

Substituting T'= 25°C in the above expression, as required by NUREG/CR-6583 to relate room temperature air data to service temp'erature data in water [7], the following is obtained:

Fen = exp (0.929 - 0.00124(25°C) - 0.101 S* T* 0* *) (5)

= exp (0.898 - 0.101 S* T* 0*0*)

(6) where [4, pp. 60 and 65]:

I, Fen S*

T*-

T 0*

=

fatigue life correction factor

=

S for 0 < sulfur content, S < 0.015 wt. %

=

0.015 for S > 0.015 wt. %

=

0forT<1500C

=

(T-150) for 150< T< 350'C

=

fluid service temperature (°C)

=

0 for dissolved oxygen, DO < 0.05 parts per million (ppm)

=

ln(DO/0.04) for 0.05 ppm < DO < 0.5 ppm ln(12.5) for DO > 0.5 ppm

=

0 for strain rate, 8* > 1%/sec

=

ln(&*) for 0.001 <

< 1%/sec

=

ln(0.001) for 8* < 0.001%/sec Bounding Fen values were determined in Reference [5]. The values determined in Table 3 of Reference [5] will be used for the carbon steel feedwater nozzle safe end location, where feedwater DO levels are low and the Fen value is a constant value of 1.74 for all temperatures for both hydrogen water chemistry (HWC) and normal water chemistry (NWC) conditions. For the low alloy steel File No.: VY-19Q-303 Revision: 0 Page 4 of 7 F0306-01 RO

Structural Integrity Associates, Inc.

nozzle comer location, the applicable F,, values are shown in Table 4 of Reference [5]. Since there is a significant variation in values with temperature, Fen values will be computed for each load pair in the detailed fatigue calculation for this location.

The environmental fatigue is determined as Uenv = (U) (Fen), where U is the original fatigue usage and Uev is the environmentally assisted fatigue (EAF) usage factor. All calculations can be found in Excel spreadsheet "VY-19Q-303 (Env. Fat. Calcs).xls" associated with this calculation.

From Table 1 of Reference [5], the following water chemistry input applies for the low alloy steel nozzle comer location:

• Over the 60-year operating life of the plant, 1WC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time.

• For the RPV Upper Region, which is applicable to the nozzle comer location, DO is 114 ppb pre-HWC and 97 ppb post-HWC.

With these assumptions, the cumulative usage factor (CUF) values documented in this calculation are considered applicable for sixty years of operation including all relevant EAF and EPU effects.

4.0 CALCULATIONS From Table 6 of Reference [6], the CUF for the safe end for 60 years of operation is 0.0571. Thus, the EAF CUF for 60 years is 0.0571 x 1.74 = 0.0994, which is less than the allowable value of 1.0 and is therefore acceptable.

The CUF for the nozzle comer for 60 years of operation is shown in Table 7 of Reference [6], and has a value of 0.0889. This calculation is reproduced in Table 1, along with EAF calculations on a load pair basis using the Fen expression in Equation (6) above for low alloy steel. The final EAF CUF for 60 years is 0.3531, which is less than the allowable value of 1.0 and is therefore acceptable. The overall Fen multiplier for this location is 3.97.

5.0 CONCLUSION

S In this calculation, EAF calculations were performed in accordance with the GALL Report [2] for the feedwater nozzle safe end (carbon steel) and nozzle corner (low alloy steel) locations. These locations were selected based on the locations identified in NUREG/CR-6260 for the older vintage GE plant and plant-specific fatigue calculations that determined the limiting locations for VY.

Calculations for the remaining NUREG/CR-6260 locations are documented in other calculations.

The EAF results for the locations identified above indicate that the fatigue usage factors, including environmental effects, are within the allowable value for 60 years of operation. The calculations for both locations make use of the 60-year projected cycles for VY and incorporate EPU effects File No.: VY-19Q-303 Page 5 of 7 Revision: 0 F0306-01 RO

V Structural Integrity Associates, Inc.

(conservatively assumed to apply for all 60 years of operation). Therefore, no additional evaluation is required for these components, and the GALL requirements are satisfied.

6.0 REFERENCES

1. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.

2. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005.

3. USAS B31.1.0 - 1967, USA Standard Code for Pressure Piping, "Power Piping," American Society of Mechanical Engineers, New York.

4.

NUREG/CR-6583 (ANL-97/18), "Effects of LWR Coolant Environments on Fatigue Design

.Curves of Carbon and Low-Alloy Steels," March 1998.

5. SI Calculation Package, Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head, Revision 0, SI File No. VY-16Q-303.

6. SI Calculation Package, ASME Code Confirmatory Fatigue Evaluation of Reactor Feedwater Nozzle, Revision 0, SI File No. VY-19Q-302.

7. EPRI/BWRVIP Memo No. 2005-271, "Potential Error in Existing Fatigue Reactor Water Environmental Effects Analyses," July 1, 2005.

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Table 1: EAF Calculations for the Feedwater Nozzle Corner QUF Ce! o'ijion ft-0 7,,N-7 of Ref,'oo'e [61:

OAF Ca'c*jiqors HWC p

NWC DO6 97 114.

667 00f-IWC =

47%0 53%

= %6 ¶400 Index Load #1.I Desci ption #1! n, (icycles Load #21 Desciptio, #2 n l(cy.'e) n (cycles) S" (poi)

K.

S" jpsi) l&*6o. -

U 1

2 2_o-osHy 6 Jl 120 16 11LoFP2 4S0 1

0 0.109 1.000 46,047 6,600.70 0.00177 2

2 2 Desof.'dF.l I

10 20 11 LOFP6 10 10 a60 6477I1 0 03164 3

2 2 2 _.' -i=s5 ydrol

." 0 16

-o FP4 10 10 0,150 100 43,204 6,632.83 j 0014, 4

2 2 D-

"*1

• i 0 11 6 3_*TolI 10 1,,

65.712 o1.O 4-,011 6,924.50 000144 6

2 2_*es'f4,1 W

4 TotbRolil 300 80 64.268 1.000 43,066 6,925,97 810 6

S 4 T.4u-rol0 l 220 3"9 256U Ibo' 123 123 63.SO6 1000 4i,430 7,73036 060158?

7 3

• _eoHy,2 I

20 5

4 TUrbonIl 67 07

1.437 1.M08 4U391 0.343 96 0 01163

.6 3'

2 4y4 I

2 2

11 [FP6 10 10 I

3134 1T006 40,101 8,624.36 05 110 6

3 2DesHy',o2 13 34 20A HSFA\\VInjl 300 13 496069 1 6'0 39,657 0810.76 0.00140 10 34 20A HSFPA',:'

287 38 HodloTes.2 I

1 4,067 1606 36,622 2,633.3 0.00011 11 34 22 HF VV64" 266 36 2i, Shdown 300 766 49,11-10M0 39,616 8,831.6 0 0'236 12 26 12 T871 2 208 36

! 2i Sh06,-[

14 14 o6043 1.0i0 38,556 6,67.40 6.014*

13 21 11 Loz47 10 26 12 l4Tfp2 274 14 49635 10M 31,091 16,10500 0604360 14 22!

13 Trio2 264 31 14 SRVBLdn I 1

4n2,902 1.606 27.510 28,831.00, 0904460 16 22 11--Lps 10 26 1 12 TGTnp2 2.3

!8 32.212 1.000 24,6387 4423'70 0.04020 16 4

o3 N up 360 26 12 _TGTnp2 253 H 3 30.212 1060 23,513 46,723.00 0.60041 17 4

i 3_S.ur 47 29 i3 '0ep,2

[

1 1

306212 1000 23, 013 46,73200 0.0002 1

4 t

46 30 i3-1 20.966 1.000 1 9,42 111116M 0.00001 19 4

3 1-S p

45 32 1 RedTo6 040 300 4S 24,.33 1.000 17,666 156 47200 0.6020 260 32 2H 33 2-0HSHeatu0*

3 *0 25 18.765 1.000 12,083 761.436 0 0.60033 21 13 I: 10A3FOyp, j 70 33 2

201 Hetup 1 45 4

19.637 1000 12,67 8706961'.30 003000 22 1' -,

-1 64ypl :

26 3

A 200A-HSFWj2.

00 3'

20.360 1.00 12624 64634 63 0.00D03 23 35

20A-HSF-2::

275 37 224 HydoTeso1 1

196.E0 1.000 12,359 in01ie 0000003 24 69 06-Vk4yRedl 2K00 30 120oA HSFWIi2l 274 274 19,341 1.000 116*52 innie 0.00303 Total. Ue

.08. 3 lrnaoen MTx,'u 4e 3ture" Fom "¢ ALL" Index Load *I Desctipion #1 nj (cycosl Load #21 Descripion #2 Ind-31 sl T01 a

0 2 (-I S (poi)

T('F) 1 2

2 2_13esH rlo :

120 16 11 LtoP2 1

2 30 16 14 65,109 356 2

2 2'DHd,1 110 20 11-LoP6 2

06 20 3

50,344 361 3

2

-_-sHydrl 3 640 16 11-L 4

30 18 7

50.163 369 4

2 2 20eslydr,1 90 11

• T.,bTfil 4

2 S0 11 6

60,712 351 5

2

.2_.*

,ydrol s6 4_-t*nI,1 36 5

12 64,266 360 6

5 4Tu HonI1 326 3

25 Unbot 6

12 39 23 63,303 360 7 3

• 2 o2 i 120 4 f4T o6il 7

1 5

12 61,437 360 8

3 2 _-4sydro2

23.

23 11 LoP9 0

1 23 7

63,130 353 9

3 2 _

osHyd.2 13 34 12A_HSFWinjl 3

1 34 21 46.066 366 10 34 Io II 670A_

nI 2'7 31 24_,oTh"2 10 34 21 38 1

496.67 388

11.

34 20AHSF0VOrj'I 206 36 2

Sh'tdown 11 21 36 1&6 49,111 388 12 26 12_G-,p2 "2B8 36 21 Shtro1 n 12 26 6

36 106 60,376 346 13 21 i 11tLoP 10 26 12 TCGTp2 613 2t 8S 26 7

49,395 424 14 26 12 TG7Tri2 264 31

'14 SRVBI',dn 14 26 6

31 41 42,602 39

165, 32'2 11 LoFP 10 2A

• 12_TGTnp2 15 22:

1 26 7

32.212 536 16 4

3_-'st'up 30 26 I 12_TTp2 16 4

1 26 7

30,212 5

603 17 4

3_tamp 47 25 130,,em12 V

4 1

26 7

30.212 603 16 4

3 Staup 46 26 13 Oeo,1 16 4

1 28 1

20,966 003 19 4

• 3-st.Ip 4*

32 6

13 0dTo706 t

19 0

1 32

. 46 24,083 003 20 32

1_RedToaoc0 255 33 I 2O[HSHeato' 20 32 6

33 26 16.766

.43 21 1'

' ý*_FW" =yp' 70 33 23 HSIeatu0

21.

13 23 33 26 16.637 046 22 1

1 G:

HSYp! !

25 35 20 HSF*nj2 22 23 3

14 20,366 046 27 f'WoTes,'1 03 Y

14 37 1

16.660 54a 20 65 6 mF*ý-d.

206 37 12 ASP '12 14

___3 16 30 14 19.341 046 T-, ('F) 0 IT., ('C) 6360 F-,0 WIC F,,*6n,,.,

306 0 16.0 3.242 3 410 0300589 361.0 1*3.9

,687 36971 60692 3890 19"6' 3.842 4.16S 0.30586 351.0 1772 3159 3066 0.0046 36o.0 122 3,309 3464 063 3660 1822 j309 3 4 O4 03416 360' 1--22

- 309 3.494 0U346 H3 0 176.3 3.192 3346 6.60-,a 368.0 17*T 3,823 4.144 0.30058 38 0 197.6 3.823 4.114 0.004' 3060 1976 3623 4.144 0.1292' 3469.

176-i 1127 3.26S 0 3046*

4240 217.8 4601 6.160 6000*08

349, 1761

ý 127 3.2668

.20011

-038 p

• 1 6.277 103336 0.0233 503.0 2615

.912 8,347 6341-4

03 0 2617

.912 8.347 0.30010 5030 261 7 6.912 8347 63000*

503' 2617

.0612 86347 030022' 5430 p 30.3 8.463 10.649 010 3M 6460 2.'

'.714 10.678

000b, 0460 2872 8.759 11.845 0D2027 548 0

2M6, 8.714 10.670 03000,0 040 1 286.7 1

714 101976 03.0000 Total, Uo..,., = 0.35306 Overall F,, -

3.970 Notes

1. T-i the max 0*0.04* lem~erat a,

n.

twf 16 rd0jst~.ad're-stem IWOplo 11100 onsoo¶~

o dI tempnnut at the010*366 lai-Wn420 661.3alyzsd T.s is*~1 deta-in'ed hor the V0660661 ootp4i I4Pforn ofaene.

which0E *cljds a*s -'rn 6t 0e'1**ient Nlaxi.mon Teo'.peRatures 1*610e a00*6.

2. F-ze cornputed*0¶.5ing E6000000*

(601006S' c--st*01061set io m-ax~im,mvslue wO.015, a*d 1*0 60*410*70 strain rate conooooo.ooy -

to lan'ocoimm *010f in i6.0.01 =-590 Ifnaf loaoiod Po.-

3. f_ =0 *U x-10 F_ x6000

% H 12+*i,4360C F

• 6060).

T, and 72 eoreeent¶ th foad -,obe, for toad 61 -a00 Load #2, re*spective',0 and a*l

• 20*00* ¶6*pia h state orumbo fow each of fts*00*040.

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