ML20062D808

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Forwards Wses 3,Fracture Toughness Test & Eval,Suppl 1 (Nov 1978),providing Further Discussion & Comparisons of 10CFR50.55a Requirements Re Subj Facil.Follows Up 781025 Discussions
ML20062D808
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/10/1978
From: Aswell D
LOUISIANA POWER & LIGHT CO.
To: Baer R
Office of Nuclear Reactor Regulation
References
LPL-9992, NUDOCS 7811300233
Download: ML20062D808 (24)
v • d • e


Text

,

l_0 UISI AN A P O W E A & L i G H T! P O 8OX 6008

  • 342 ca,acNce srater NEW CALEANS LCuiSIANA 70174. (504) 366-2345 Midsvsy[G N vember 10, 1978 a

0 L ASWELL Vce Pres 4eet-Powee Pmducton LPL 9992 3-A34.02.01

{/

Mr. R. L. Baer, Chief Branch No. 2 s

Light Water Reactors Division of Project fUnagement U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Supplement I to 10 CFR 50.55a Letter

REFERENCE:

Letter LPL 8254 dated February 24, 1978

Dear Mr. Baer:

In follow-up to discussions between Messrs. D. B. Lester and R. W. Prados of LP&L and Messrs. R. Benedict and R.

Hermann of the NRC on October 25, 1978, we are submitting Supplement I to the above Reference.

This supplement pro-vides further discussion and comparisons of 10 CFR 50.55a requirements affecting Waterford 3.

If you have any further questions, please advise.

(

Yours very truly, D. L. Aswell DLA/RWP/dd cc:

W. M. Stevenson E. Blake

\\f 7811300A33A

(

WSES 3 FRACTURE TOUGHNESS TESTING e

AND EVALUATIONS SUPPLEMENT I (Nov.1978)

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l I

INTRODUCTION A report providing the results of fracture toughness testing performed on Waterford 3 naterials and an evaluation of compliance with 10CFR50.55a was submitted for NRC review by Louisiana Power and Light.

(Letter, 'fr.

D.

L. Aswell to Mr. Karl Kniel, LPL 8254, February 24, 1978).

This supplement has been prepared to assist in the NRC review and contains further discussion and comparison's of the code requirerents affecting the Waterford 3 materials.

Tables I, II, IV and VI and Figures 28 and 29 are included for completeness.

These tables are identical copies of the corresponding tables in the original report (LPL 8254).

?

Attachnent I is a tabular comparison indicating compliance status of reactor vessel surveillance criteria requirements in accordance with Appendices G and H.

i 9

Waterford Construction Permit (11/14/74)

Component: Reactor Vessel Code Used:

Requirements:

Appendix G Requirements 1971 Summer See Table A See Table A Section III A Compliance: C-E complies with all 1971 Sunmer Addenda fracture toughness requirements.

To present the fracture toughness data as required by Appendix G to the maximum extent practical, the available test data for the reactor vessel has been evaluated according to Branch Technical Position MTEB 5-2 " Fracture Toughness Requirements". This approach, which was recommended by the NRC Staff at the Dec.,1974 meeting results in a downgrading of the material fracture toughness properties and provides more conservatism than if the testing actually were performed in accordance with 10CFR50, Appendix G.

The available

', fracture toughness data are reported in attached Table I.

Footnotes in the attached ibles indicate the sections of MTEB 5-2 that were used in evaluating the data.

Non compliance, Appendix G.

No weld metal or heat affected zone (HAZ) material was tested. However, conservatism in the evaluations of Waterford primary system pressure boundary ferritic materials has b:en confirmed by testing performed in accordance with Appendix G of Part-50.

In addition to the Charpy impact testing conducted with test specimens prepared from longitudinal (strong direction) material, Charpy impact testing on transverse (weak direction) material and drop weight tests on base metal, we'ds and HAZ materials for the most limiting reactor vessel beltline material have been performed. Materials for the most limiting area in the beltline region had been set aside and retained for purposes of performing baseline testing as part of Waterford's reactor vessel material surveillance program.

Following the December,1974, meeting, we elected not to wait to p+rform our baseline tasting of the limiting plate in the beltline region as is customarily done. We advanced d(tha schedule for this testing and have now completed it.

The results, tabulated in lble VI attached, when contrasted with the results of our MTEB 5-2 evaluations, demon-strate the wide margin of conservatism in our evaluation technique.

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r TT3LE I WATEPJOR:: UNIT 3 REACTOR YESSEL FRACTURE TC'JGHNESS CATA (Sheet 2 of 2)

Charpy 30 f t-lb.

Charpy 50 f t-1b. 35 Xtis 1.eteral Cta py C :er RT..[

Fix Tc ;. ('F)

Fix Te p ('F)

Ex;ansion Te p('F) Er rry (f t-i Drop Pfece Drawt g Code Weicht f;.-t e -

t.:-der Nf-ter Pe terf el Vessel L cation NOTTl'F)

I. I leno.

Trecs. t en q.

Tra ns.

le-t-Tre nt.

.te-e., T-a-SA533-Inter-124-102 741701 6103 H-1C03-1 B.CL-1 rediate Shell Plate

-30

-30

-30

-10

-10 1 *4 5A533-Inter-124-102 741701 6103 M-1C03-2 2.7.-1 cediate Shell Plate

-50

-30 -15

' 12 149 51.533-Inter-12"-102 741701 6103 M-1003-3 B.CL-1 rediate Shell Plate

-50

-42 -10

-2 133 /1 -

5*533-

\\)

122-102 741701 6103 M-1CC2-1 B.CL-1 Upper Shell Plate

-40

+10

+13 -

+32

+23 151 SA533-122-102 741701 6103 M-1002-2 0.CL-1 Upper Shell Plate

-20 0

-20 ;

+12

+15 123 57,533-122-102 741701 6103 M-1032-3 C.CL-1 Upper Shell, Plate

-40

-40

-20 t'

0 153 0

54533-154-102 741701 6103.M-1007-1 0.CL-1 tottem Head Torus

-80

-80

-72

-62

-60 17*

5 A533-

- - -152-101 741701 6103 M-1CCB-1 U.CL-1 Bottom Head Core

-40

-30

-35

-10

-15 114 57.533-IC:-1C2 7*1701 6103 M-1005-1 S.CL-1 Closure. Head Torus

-30

-30

-25 0

-2 150 SM 33-142-101 741701 6103 M-1004-1 0.CL-1 Lower Shell Plate

-50 0

10 '

25 '

-20 163 SA533-

~

142-101 741701 6103 M-1C04-2 0.CL-1 Lower' Shell Plate

-20

+22 37 62 55 144 5 4 33-142-101 741701 6103 M-1CC4-3 D.CL-1 Lover Shell Plate

-50 0

12 33 25 145 SA533-102-101 741701 6103 M-1CCS-1 D.CL-1 Closure Head Do e

-50 0

-5

+15

+10 133 e

-~

..L N..., _

=., _ __ 1 - _ _,.:..'

. = _

I TABLE VI SU?SIARY.0F SURVEILLANCE MATERTALS TESTING 30 f t-lb 50 ft-lb 35 Mils Lat.

RT Yield a

b b

.C Upper Shelf Fix Fix Exp. Fix NDTT RT Strength (ksi) y NDT Haterial and Code (ft-lb)

(*F)

(*F)

(*F)

(*F)

(*F)

Static Dynamic Base Metal Plate 136

- 30 18

-2

-20

-20 69 97 H-1004-2 (WR)

Base !!etal Plate 169.5 0

48

' 36 0

70 103-H-1004-2(RW)

L' eld Metal

'146

- 76

-46

-46

-80

-80 85 113 11-1004-1/M-1004-3 IIAI Metal 163.5

-106

-72

-76

-50

~50 70 113 11-1004-2 SRllllSST 130 28 70 48 0

Plate OlHY-RW a Determined from average impact energy curve.

b Determined from lower bound curve.

Wate'rford Construction Permit (11/14/74)

Component: Steam Generator Primary Side Only Code Used:

Requirements:

Appendix G Requirements 1971 Summer See Table A See Table A Sect. III A

~

Compliance:

CE complies with all 1971 fracture toughness requirements.

Non Compliance: No weld metal, heat affected zone or transverse

(

Appendix G plate testing was performed. No drop weight testing was perfo rmed. No available material exists for performing these tests at this time.

To present the fracture toughness data as required by Appendix G to the maximum extent practical, the available test data for the steam generators has been evaluated according to Branch Technical Position MTEB 5-2 " Fracture Toughness Requirements". This approach, which was recommended by the NRC Staff at the Dec.,1974 meeting results in a downgrading of the material fracture toughness properties and provides more conservatism than if the testing actually were performed in accordance with 10CFR50, Appendix G.

The available fracture toughness data are reported in attached Table IV. Footnotes in the attached tables indicate the sections of MTEB 5-2 that were used in evaluating

(

the da ta.

i

m TABIE IV WATERFOR3 U:117 3 STEAM GI:E7* TOR yl.TE". *LS F7.*CTi'RE TC*J0iNE55 CATA (SiEET1 of 3)

Mils Let. E n. Mils tet. E c Charpy Energy Charpy) Energy ft-lbs at 150' at O' Festtien et IE0*

FMithn Tes. U -bs) et 0 Pest:1ca.

Crop RT,3T Temp rosition

%-tea

?;r-t e r N :-be r l'ateriel Loettien ICTT ('F)

(*F)

(*F) 1 2

3 Avg _

1 2 3 Ave 1

2 3 Av;.

1 7 3 Ac Piece

're.<f n; Code Welsht 252-201 E-74273-251-003 C2317-1 5A533CL2 Stay Cy).

I;A IC^

10 79 S8 78 83.7 65 33 53 51.7 47 43 47 47.3

  • 2: 2 :*

212-I:1 E-7(270-251-033 C3017-2 SA503Cl2 Stey Cyl.

fA 10^

10 79 08 78 81.7 65 39 53 51.7 47 48 47 47.3 43 22 22 2*

(1)

E-74270-26;-003 C5025-1 5AE00"L2 (1) fiA 23 10 74 64 73 70.0 31 45 32 35 56 54 54 54.7 2* 2: II

  • 3 (1)

E-7:270 251-033 C3C25-2 5A500L2 (1) fiA 10^

10 93 91 95 92.3 111 S2 95 9?.3 73 75 E3 75 E2 7 E5 ;*

251-231 E-74273-251-C33 C5033-1 SA500CL2 Outlet tiozzle fiA 10" 10 82 74 72 76 E4 81 (3 77.7 63 (C 61 C4.3 73

1 C 212 231 E-7 270 251-003 C3:33 2 5A5C3CL2 Catlet r:oz:le I:A 10 10 65 33 79 60.7 ES 61 75 73.7 60 34 (5 53 (9.I A !~ t A

253-201 E-74273-251-033 CSC03-3 5A50CCL2 Outlet Nozzle fiA 10 10 59 48 70 59 60 65 62 62.3 49 33 54 47.3 55 E7 E:E!

A 253-231 E-7(273-261-C33 C9003 4 SA532CL2 Outlet toozzle

!!A 10 10 61 41 81 61 64 55 E2 67.

47 35 C3 47.7 49 24 70!"

A 253-131 E-74273-261-033 C9C04-1 SALO20L2 Inlet ::ozzle

  • f(A 10 10 85 75 62 74 08 95 49 77.3 70 52 51 61.0 E3 75 47(:

A 2iE-101 E-74270-251-033 C9:0*-2 SA530CL2 Inlet f:ozzle I:A 10 10 70 65 34 50.3 35 61 66 54.3 62 57 44 54.3 47 53 E: 5:

A

~

255 *:2 E-7'273-251 C33 C9335-l' SA500CLI outlet i:ozzle SE f;A 10 10 50 77 103 78.3 105 73 94 $3.7 75 71 79 75.0 105 55 S: 2, A

25S 432 E-74273 251 G03 C9335-2 SA538CLI cutlet riozzle SE i:A 10 10 50 77 108 78.3 1C5 73 94 93.7 75 71 70 75.0 135 (5 5 E A

2EE-4:2 E-74270-251-C33 C9035-3 5A538CL1 Outlet ::ozzle SE t;A 10 10 75 71 79 75.0 105 65 90 E5.7 73 64 71 CC 3 C5 (2 El 7-A 253 *32 E-74273-251-C03 C93C5-4 5A50cCL1 Outlet fior:Ic 5E f:A 10 10 75 71 79 75.0 105 65 S3 85.7 70 64 71 E3.3 E5 22 E17 A

213-2:2 E-74273-251-003 C5035-1 SA500CL) Inlet f:ozzle SE

!;A 10 10 50 52 54 52.0 53 45 59 52.7 5*

37 52 47.1 55 41 Sf I A

~ 25E-2 2 E-742 73-251-C03 CS306-2 5A500CL) inlet Iozzle SE

!;A 10 10 50 52 54 52.0 53 46 59 52.7 54 07 52 47.7 55 4 is t A

252-201 E-74273-251-033 C0318-1 5A53CCL2 Stay Ring 1A 10 10 03 47 47 53.0 56 65 76' 65.7 63 ** 43 53.0 5? 55 53!

A 252-201 E-7

  • 273-251-033 C9318-2 SA502Cl2 Stay Rin9
A

'10 10 52 61 79 04.0 62 43 74 61.3 45 $2 E5 53.0 52*3C:5 E-7*273-251-003 C9026-1 5*100CL) Cyl Safe End IA 13 10 105 105 110 137 83 84 75 79.7 87 65 SI E7.7 7 ' " 71 '

A E-74270- 251-C')3 C5025 2 SA50E'L1 Cy1 Safe End i:A 10 10 105 105 110 107.

80 84 75 73.7 67 ila 91 E7.7 7

71 7 A

245-101 E-7

  • 2 70- 251-C33 CC2/1-1 SASCECL2 Tube Sheet i:A 10 10 81 81 E3 31.7 61 53 55 55.3 59 60 62 E3.3 43 23 23 :

~

A 2*S-131 E-74273-251-CO3 C8821-2 SA508:L2 Tube Sheet f:A,

10 10 70 45 67 60.7 85 EO ES 77.0 52 35 50 43 64 47 531,

A

1) To be supplied by a:acnd[::ent to the FSAR
  • Paragraph 1.1 (4), Average of 3 tests at a single ter;erature > 45 f t-1bs.

A MTE3 Positico 5 2. -f racture Toaghness F.equircr ent" Average of 3 tests at a single temperature > 33 < 45 f t-ths.

~

8 MTE3 P:51:1cn 5-2. -Fracture Toughness Require:ent'!

Paragraph 1.1 Paragraph 1.1.(3)b Average of 3 tests C MTE3 Pcsttien 5-2, " Fracture Tcushness Requirementi I

r - -

P TABIE DT WATERFORD INIT 3 STEAM CE:;ERATOR F%TERIA*.S FRACTURE TOUGMXESS CATA (SNEET 2 of 3)

Ch rpy Er.crgy Cherpy En:rgy P.11s Let. Eks. P.11s tat Emp t ]{p"'

At O' Pesttf on RT.'3T Test (f t-15:) et 0*

(f t-ibs) at 183, Crop P!e:e Crawir.g Code Weight Tc7 Pesition resition I

  • - er t;-See E.-ber Material tocation KDIT (*F)

(*F)_

(*F) 1 2

3 Ave _

1 2

3 Ave _ 1 2 3 Ave.

1 2 3 v.

10 10 37 66 79 66.7 93 115 63 $3.2 35 5* ES 51.7 67 7S 52 EE..

A

~

243-131 E74270-251-033 CE225-1 SASCE;t2 Stay Stub

^

10^

10 80 93 89 E5.3 68 105 E3 E4.7 32 ES 55 51.7 f3 52 CO 63.0 2:3-101 E7*270-251-033 C8325-2 SA5030t2 Stay Stub (1)

E74270-251-C33 CEC 23-1 SA5CECL1 (1) 30 10 37 35 3S 35.7 31 23 32 33.3 31 33 35'33.0 23 25 I? 27.:

3 (i)

E7:273-251-CO3 CE329-2 SA5020L1 (1) 03 10 37 35 33 35.7 31 23 32 30.3 31 33 35 33.0 23 25 ?? 27.'

3 (1

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TABLE IV WATERFORD UNIT 3 STEAM GENERATOR l'ATEr.!ALS FPACTU-~ wUGSNESS DATA (SEEET 3 CF 3)

Cher;y Energy Mtis lateral Crop RT Test (f t-its) et O' E-;a sie-Pie:e Drawing Code Weight

  • DT

-Terp F:sition

-t er
.-See f* rber Materfel LScation CT~ (*F)

('F)

(*F) 1 3

Avg.

1 2 0 *ve 8

M 31 M 32 31.0 2? 25 23 2M Za*-102 E74270-251-003 CC*23-1 SA532 CL1 Tube Sheet Extension NA 30 B

10 43 51 30 37.0 27 35 22 22.3 254-102 E74270-251-C33 C9002-1 SA533 CL1 Prl: ary Head 30 0

25*-102 E742 70-251-C03 C9002-2 SA532;CL1 Prinary Head 30 10 33 27 43 33.3 21 19 31 23.7 8

31 O?g 0.3 25*-i:2 E 7a 270-251-033 C9002-3 5A5333CL1 Prir.ary Head 20 10 41 45 45 43.7 23 25*-102 E7 270-25;-C03 C5002-4 SA533:CL1 Prirur/ Head 40 23 41 39 28 35 23 27 2y 5.3 25*-102 E7:273-261-C33 C9332-5 SA5333CL1 Prir.:ary Head 43 20 43 25 3*

74.3 31 22 27 25.5 A

275-101 E 7:2 70-261-CO3 CSC07-1 5A5333CL2 Top Head 10 10 64 51 72 62.3 41 35 f: ~ 2. 3 4

(1)

E74270-251-C03 C9038-1 S A515G't73 Top Head 10 13 62 94 71 75.7 45 E9 54 ES 3

(1)

E74273-251-C33 C9002-2 SA51EG't70 Top Head 30 10 31 31 33 30.7 23 35 3*

35 A

(1)

E74273-261-C03 C9003-3 5A51CGR70 Top Head.

10 10 53 54 56.

5*.3 33 33 43 33 10^

10 70 C5 SS 64.7 49 45 33 40.0 (1)

E7 273-261-C33 C9000-4 SA515GR70 Top Head 10^

10 72 74 76 74 59 55 61 53.7 (1)

E74270-261-003 C9023-1 SA5333CL1 (1)

A (1)

E 74270-261-003 C9024-1 SA5323CL1 (1) 10 10 E3 72 63 73.3 52 54 E

  • 55.7 A

242-201 E74270-261-003 C8226 SA515G270 Stay Cap 10 10 112 07 ES 98.3 S3 77 6*

76.3 (1

O e

I 0

9 I

l l

1 Water' ford Construction Permit (11/14/78)

Component: Pressurizer-Code Used:

Requirements:

Appendix G Requirements:

1971 Summer See Table A See Table A Sect. III A Compliance: C-E complies with all 1971 fracture toughness requirements.

Non Compliance: No weld metal, heat affected zone, or transverse Appendix G plate testing was performed. No drop weight testing was 1

performed. Forgings were tested at high stressed locations, not with specimens normal to principal direction of working.

No available material exists for perfonning these tests at this time.

To present the fracture toughness data as required by Appendix G to the maximum extent practical, the available test data for the pressurizer has been evaluated according to Branch Technical Position MTEB 5-2 " Fracture Toughness Requirements".

This approach, which was recanmended by the NRC Staff at the Dec.,1974 meeting results in a downgrading of the material fracture toughness properties and provides more conservatism than if the testing actually were performed in accordance with 10CFR50, Appendix G.

The available

(

fracture toughness data are reported in attached Table III. Footnotes in the attached tables indicate the sections of MTEB 5-2 that were used in evaluating the data.

i

^

TIGE,E III WATERTORD UNIT 3 PRESSURIZER F/JERIA*.S FRACTURE TOUCHNESS CATA (SHEET 1 OP 1)

Charpy Energy Charpy Energy Mils Let. Exp.

Etistat: Esp.

At c' F:51tien A: 123* hsit Drop RT Test (ft-lbs) at C*

(f t-ibs) et 100 Pfece Drawing Code Weight r:3T Terp Fosition Pesition X.-etr Nu-ter Nu-5er Ma terial location fi3TT ('F) (*F)

(*F) 1 2

3 Avg 1

2 3

Avg _

1 2 3

Ave _

1 2 3 Ag 653-101 Ef51-C02-03 P.2001-1 SA50CC 2 Surge Nozzle

-50

-30

+10 110 104 101 105 105 126 99 110 82 71 74 75.7 73 E" 73 75.7 0

i' 3-l";l EC51-002-03 F2502-1 SA5:30 2 Spray riozzle

-50 0

-20 28 34 35 32.3 51 30 25 35.3 29 31 33 31 37 29 25 30.3 0

f;:-2;l Efil-CO?-03 P2CO3-1 SASCSC 2 Safety Valve Nez -50

-30

+10 135 123 97 117 23 119 143 115 23 73 72 79.7 C3 E2 S: 21.7 C

f:3-201 Ef51 002-03 M2633-2 5'50EC 2 Safety Valve Nor -50

-30

+10 135 120 97 117 ES 119 140 115 E9 73 72 79.7 (3 EZ 11.'

C E55-101 Ef 51-002-03 M2511-1 SA50EC 2 Support Forging. -50

-30

+10~ 133 1 31 121 127 118 97 103 135 95 E4 E3 E3.3 E4 75.4 7s.7 C

Charpy Energy Mills Latcral Assorbed Espansten 1

2 3

Avc 1 2 3

Avg C-642-101 E651-002-03 M2606-2 SA5333CLI Shell Plate.

-50

-30

+10 78 79 73 76.6 53 53 47 51 (Lower) 3 235-203 E551-C02-03 M2510-1 SA5333CLI Tcp Head

+30

+33

+10 42 3S 50 42.7 45 46 35 42.7 3

~ 225-2 3 E551-C32-03 !!2510-SA533*:CL1 Dottoa I! cad

+33

+33

+10 44 35 34 37.7 42 3' E3 3G.3 3

~.

E73-102 E651-002-03 M2537-SA51CGR70 Supp. Ring

+30

+30

+10 39 34 56 43 33 44 33 33.3 Flance 673-104 ESSI-C32-03 !!253S-1 SA5165270 Supp. Ring

.-50

-33

+10 77 85 81 81 65 65 60 63.3' C

sep ent C

675-132 Ef51-C02-03 M3529-1 SA516C170 !!anuay Cover

-50

-30

+10 51 65 51 55.6 73 68 C4 53.3 f22-102 'EC51-C32-03 M2605-1 5A533acLI Urrer Shell

+10

+10^

+10 55 43 44 47.3 36 27 25 29.9 Plate C

(22-102 EE51-002-03 M2605-2 SA533xt1 upper Shell

-50

-30

+10 50 59 59 58.7 41 40 39 43 Plate 642-102 Ef 51-C02-03 M26CS-1 SA5333CL1 teuer shell

+30

+30

+10 40 43 48 43.7

-26 27 32 2E.3 Plate A M!E3 Pesition 5-2,

  • Fracture Toughness Requirements %

rC* Paragraph 1.1 (4), Average of 3 tests at a single terperature > 45 ft-1bs.

Paragraph 1.1 (4), Average of 3 tests at a single te:;erature > 33 <c5 f t-1bs.

S M*E3 F:stiton 5-2, " Fracture Toug5r.ess Requircrents"-

Pa-agraph 1.1 (3)b C Y.'I3 F:stilen 5-2, " Fracture Touchr. css Require: cats"-

TABLE A REACTOR C[. ANT SYSTEM' COMPONENT MATE

'L 6

FRACTURE TOUGilNESS TESTING REQUIREMENTS Through Sumner FEDERAL REGULATION 1971 ASME CODE 1972 SUMMER ADDENDA TO THE 10CFR PART 50 APPENDIX G CRITERIA SECTION III 1971 ASME CODE SECTION 111 (JULY 1973)

ORIENTATION OF NO ORIENTATION REQUIRE-

1. PLATE MATERIAL SPECIMENS ARE TO BE SAME AS 1972 SUMMER CHARPY V NOTCH MENT, PRACTICE HAS BEEN ORIENIED IN A DIRECTION NORMAL ADDENDA (Cv) IMPACT TEST TO TAKE SPECIMENS TO TiiE PRINCIPAL ROLLING DIRECTION SECTION 111 S?ECIMENS PARALLEL TO THE DIRECTION OF THE MATERIAL (OTHER.HAN THE OF THE PRINCIPAL ROLLING THICKNESS DIRECTION)
2. IN ADDITION, MATERIALS SUBJECT TO IIIGli NEUTRON IRRADIATION (BELT LINE PLATES) THE Cv SPECIMENS SHALL ALSO BE ORIENTED IN THE DIRECTION PARALLEL TO THE PRINCIPAL ROLLING DIRECTION
3. FORGING MATERIAL (NOZZLES)

SPECIMENS ARE TO BE ORIENTED IN

~

A DIRECIlON NORMAL TO THE PRINCIPAL DIRECTION THE MATERIAL WAS WORKED (OTHER TilAN THE THICKNESS DIRECTION)

O

e

~

TABLE A REACTOR s JLANT SYSTEM COMPONENT MA'1 IAL FRACTURE TOUGIINESS TESTING REQUIREMENTS (Cont'd)

Through Summer FEDERAL REGU LATION 1971 ASME CODE 1972 SUMMER ADDENDA TO THE 10CFR PART 50 A??END!X CRITERIA SECTION 111 1971 ASME CODE SECTION III (3gty j773)

TEST REQUIREMENTS APPLIES TC BASE METAL APPLIES TO WELD METAL, HEAT AFFECTED APP LIE S T O '.~i E LD t.'.E T AS ONE (HAZ) AND BASE METAL HEAT AFFECTED ZO.'.E AND ACCEPTANCE ONLY

1. ESTABLISH A REFERENCE TEMPERATURE (HAZ) AND BASE t.'.ETAL STANDARDS
1. TEST TiiREE Cv SPECIMENS (RTNDT) BY:
1. SAM E AS 1972jU'.'.*.'.ER AT 60 F BELOW THE LOWEST SERVICE TEMPERATURE,
o. DETERMINING A TEMPERATURE (TNDT)

ALSO 60*F BELOW Tile Wi!ICil IS AT OR ABOVE Tile N!L-DUCTILITY IlYDROSTATIC OR TRANSITION TEMPERATURE AS DETERMINED 2. IN ADDITION, FOR

[ GIT PNEUMATIC TEST METAL BY DRCP WE! Gilt TESTS C

'E TEtAPERATURE

(. A.T A TEMPERATURE NOT GREATER THAN BELT Llib

o. TiiE ABSORBED ENERGY (T '

+ 60*F) TEST THREE Cv 4fECIMENS VALUE OF THE Cv Wl,llbi SilALL EXfilBIT AT llA'ST 35 MILS 2.Cv TESTS SHALL BE SPECIMENS SliALL BE LATERAL EXPANSION AND NOT LESS CONDUCTED AT 30 FT-LBS MINIMUM.

TilAN 50 FT-LBS OF ABSORBED ENERGY, APPROPP.! ATE TEM?ER-LATERAL EXPANSION IN WillCil CASE TNDT IS THE REFERENCE ATURES Ci'ER A AND % SilEAR FRACTURE TEMPERATURE T E.'.'.3 ER ATU.?.E ? a N G E DE m

iO//EV R Tl RE E

c. IF Tile ABOVE STEP 15 NOT MET, CONDUCT 7[5 ADDITIONAL Cv TESTS TO DETERMINE NO MINIMUM REQUIRE-(INCLUDING iHE UFFER M E NT S.

DROP WEIGHT THE TEMPERATURE (TCv) AT WHICH THEY SHELF) INC LU dim G ARE MET. IN Tills CASE, THE REFERENCE TESTING 15 NOT FRACTUF.E ENE.lGY AND TEMPERATURE REQUIRED II' Cv REQUIRE-LATERAL EXPANS!CN.

RT

-TCv - 60oF MENTS ARE MET NDT ENERGY SHALL EE A MINIMUM OF 75 FT-LSS 9

Waterford Construction Permit (11/14/74)

Component:

Reactor Coolant System Piping Requirements:

Appendix G Requirements:

Code Used:

C tests required ASME Code, Section NB 2300 and y

1971 only when required Appendix G, Section G3100 Summer by Design Spec Section III A (NA 3250) Longitudinal tests were required to demonstrate an average of 20 ft-lbs absorbed energy.

Compliance:

CE complies with all 1971 fracture toughness requirements.

Non Compliance:

No transverse impact testing, or drop weight testing was performed.

Appendix G To present the fracture toughness data as required by Appendix G to the maximum extent practical, the available test data for the reactor coolant system piping has been evaluated acco-ding to Branch Technical Position MTEB 5-2

" Fracture Toughness Requirements". The methods of MTEB 5-2,which allow the development of an RT for materials exhibiting a fracture toughness of at least 30 ft-lbs absorNd energy,were applied. Footnotes in attached Table II g

indicate which MTEB 5-2 sections were utilized in evaluating the piping. For those plates which exhibited fracture toughness energies between 20 and 30 ft-lbs a generic basis to establish a conservative RT was utilized. These plates are denoted by a footnote D in attached Table IST The Charpy energy absorbed vs temperature and the mils lateral expansion vs temperature for the Waterford Unit 3

(~

material and for the twenty-five additional heats of SA 516 Gr. 70 plate from Southern California Edison Co.'s San onofre Units 2 and 3, were plotted to establish the highest temperature necessary to achieve 50 ft-lbs absorbed energy and 35 mils lateral expansion.

(Figs. 28 and 29 respectivel ).

The highest temperature neces-f sary to achieve 50 ft-lbs absorbed energy is 118 F agd the highest temperature necessary to achieve 35 mils lateral expansion is 96 F.

A conservative RT g

NDT for this material is 58 F (T

-60).

50 ft-lbs l

l l

I

y _

^

  • TP.?LE II 1;ATEP.FOR317 TIT 3 PIPING MATERIAt.S FFACTi;RE TOUO*-iXESS DATA (SEEET 1 of 2)

Charpy Er.er'sy Mils tat. Exp.

Drop R7 Test (f t-lbs)

I.K3T Terp Pitet Drawing Code k*eight II

('F) 1 2

3 Avg.

1 2

3 A.g.

? :-r e r

-ber K :-ber Material _

Lecation ESTT(*F) 722-1C3 (1)

M2334-3 SA5153R70 Straight Seg.

!;A 303

+10 40 40 43 40 32 33 33 32.7 722-103 M2 04-5 5A515G170 Straight Seg.

333

+10 43 40 40 43 32 33 33 32.7 722-103 M230*-6 5A5163'170 Strai;ht Seg.

333

+10 40 40 40 40 32 33 33 32.7 722 1:3 M23:4-8 SA516CR70 Straight Seg.

303

+10 43 40 43 0 32 23 33 32.7 B

+10 45 43 23 23 34 33 43 34.7 742-103 H2303-1 SA5160R70 E11 Seg.

33 7 2-103 M2803-2 SA516".R70 Ell Scg.

30

+10 46 40 23 33 34 3'3 43 3*.7 0

7:2-;;3 M2003-3 SA51CCR70 E11 Seg.

303

+10 46 40 28 33 34 33 43 3*.7 7*2-1C4 l'2SCS-1 SAS.'0270 E11 Seg.

303

+10 31 52 35 33.3 32 3; 49 33.3 -

722-103 M2504-1 SA5100?.70 Straight Seg.

303

'+10 43 40 40 43 22 33 33 32.7 M2E01-3 SA51E0370 Straight Seg.,

3:3

+10 37 33 44 33 43 35 35 25 722-102 1:2c31-4 SA5160R70 Straight Seg.

3C3

+10 37 33 44 33 43 35 35 33 722-102 722-102 M1/.02-1 SA516C270 Straight Seg.

10A

+10 62 52 105 73 46 55 E2 61 722-102 M2231-1 SA516G370 Straight Seg.

SEA

+10 24 22 21 22.3 23 23 23 23 722-1G2 M2t*31-2 S;516G170 Straight Seg.

539

+10 24 22 21 22.3 23 20 20 23 7*2-102 M2!35-1 SA516GR70 Ell. Seg.

SCO

+10 33 23 32 28.3 26 31 33 29

~

7'2-106 M2537-1 SA'516GR70 Ell. Seg.

SSD

+10 25 28 28 27 21 22 22 21.7 7:2-103 M2803-4 SA516GR70 Ell. Seg.

SS3

+10 25 26 20 23.7 25 21 27 2 *. 7 722-1C3 M2SO4-2 5A5165470 Straight Seg.

550

+10 32 23 24 23 32 22 23 27.3 722-1 3 l230*-4 SA51CCR70 Straight Seg.

533

+10 32 23 24 23 32 22 23 27.3 722-103 M2804-7 SA5165270 Straight Seg.

550

+10 32 23 24 23 32.22 23 27.3 722-103 M2339-1 SA510GR70 Ell. Seg.

530

+10 25 25 31 27 23 22 23 2 ". 3 722-104 M2302-2 SA516GR70 Stral35t Seg.

SSO

+10 38 33 16 23 33 18 33 23.7

1) To te se; plied by e :end-ent t. the FSAR A MTE3 Position 5-2
  • Fracture Toughr:ess Requircrents"_~

' Paragraph 1.1 (4) Average of 3 tests at a single te=p > 45 f t.-1bs.

E Y.iE3 Pesitten 5-2

  • Fracture Toughness Ecquirexents"'

' Parag'raph 1.1 Average of 3 tests at a single temp > 33 <45 ft-lbs.

C ?S Position Sr2.* Fracture Toughness Requirecents"'

  • I.* Paragraph 1.1 (3)(b)

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=s TEMPERATURE FF)

- [ ATTACHMENT I s

^

LP&L - WATERFORD UllIT # 3 SURVEILLAfiCE CRITERIA COMPARED CRITERIA (1ETil0D EFFECTIVE 1971 METHOD EFFECTIVE 1973 COMPLIANCE DEFII;ITI0:1 0F VESSEL SilELL MATERIAL ('IllCLUDIllG HELD SAME AS 1971 PLUS ANY YES SELTLII;E AND liAZ) DIRECTLY SURROUNDIllG ADDITI0tlAL MATERIAL

' ppg. DIX G l

EFFECTIVE llEIGilT OF FUEL ELEMENT WilERE RT FtnT (ADJ) AT ASSEllBLY E0L> SO SU3 JECT PLATE SELECTION PLATE llITH llIGilEST DW NDT C011 bit!ATI0ll BASED Oil PLATE SELECT-IO ;*

HIGilEST RTHDT; CU AND P BASED 0:1 (APPEllDIX H)

C0llTENT Allu CIIARPY-V LO::GITUDIliAL UPPER SilELF DATA SPECIMEli ORIENTATION L0flGITUDINAL (RW OR STRONG)

TRANSVERSE (WR OR WEAK)

YES, FOR SURVEIL :

APPENDICES G Afl011 LAtlCE MATERIALS

.U:lIRRADIATED UPPER SHELF NO REQUIREMENT 75 FT-LBS Cv ABSORBED YES

, !:;IMU!1 - CORE BELTLINE ENERGY MATERIALS AFPEllDIX G

0. OF IRRADIATI0ft CAPSULES 3 CAPSULE MINIMUM 3 TO 5 CAPSULE MINIMUM YES DEPENDEllT ON MAX VALUE

.PPENDIX 11 0F RT DT (ADJ), PREDICTED N

FOR EOL

  • BASED ON RT FR0f1 LONGITUDINAL DATA, HIGHEST CU/PH0S AND FLUENCE. TO ESTABLISH MOST LIMITING PLATE FOR SURVEILLANCgDJROGRAM(LOWERSilELLM-1004-2) 4

E C

l:A I

L A.

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r'5 ATTACIDENT I (Cont'd) s

^

LP&L - HATERFORD UNIT # 3 SURVEILLANCE CRITERIA COMPARED CRITERIA METil0D EFFECTIVE 1971 METil0D EFFECTIVE 1973 CG:1PLIANCE ACCELERATED CAPSULES OPTI0tlAL - t10 CREDIT ALLOWED OPTIONAL. REl10 VAL SCilEDULES it. A.

(AF F ENDIX 11)

REQUIRE AEC APPROVAL E:;ERGY FIX - flDTT OR CV 30 FT-LB LEVEL CV 50 FT-LB LEVEL OR 35 f4ILS YES RT::DT SilIFT LATERAL EXPAllSI0tl WilICil-EVER IS GREATER (APPE!! DIX 11)

!aRADIATI0ll SilIFT HDTT(UNIRR.)[FROM DW TEST] +

HDT (UllIRR.) [FROM DW TEST YES RT (APPEllDIX 11) flDTT (igg,) [FRGM SilIFT Ill AllD CV TESTS] + RT:DT (IRR.)

l CV CURVE AT 30 FT-LBS.]

[FR014 SilIFT IN CV CURVE AT 50 FT-LBS OR 35 tills]

IRRADIATED UPPER NO REQUIREMENT 50 FT-LBS YES Sl! ELF !!IllII'U:4 EELTLI :E !%TERIALS VESSEL AfillEALIllG NO SPECIFIC REQUIREMENT IF MAX PREDICTED RT (ADJ)

YES ilDT

>200 F TilERMAL AtlNEALING 110ST BE POSSIBLE O

g

AITAC11 MENT I (Cent'd)

LPl.L - WATERf0B0 UllIT # 3 i'

COMPARIS0ff 0F REQUIRED AfiD PRESE!iT CAPSULE REl10 VAL SCllEDULES l

.it 1

\\

10CFR50 APPEi1 DIX 11 PRESEllT SCHEDULE ib i-TARGET TARGET WITilDRAUAL FLUE:CE CAPSULE AZIMUTitAL UITilDRAWAL FLUEllgE 10.

LOCATI0tl REQUIREllEllTS TIMES (YRS)

(n/cm )

TIllES (URS)

(n/cn2)

IO 18

. -[

2 97*

RTilDT(ADJ)-50 F OR 7

6.0x10 7

6.0'x10 1/4Til SERVICE LIFE UllICilEVER IS EARLIER i-l9 I9

.l -

3 104" "1/2 TIME IllTERVAL

'19 1.6x10 19 1.6x10 e

BETUEEft IST AllD 3RD l-CAPSULE HIlllDRAWAL I9 I9 4

284*

t'3/4 TIME IllTERVAL 30 2.5x10 30 2.5x10

'i '

CETUEEit 1ST AllD 3RD l-CAPSULE HITliDRAWAL

'i 5

263' STAllDBY STAtiDBY

.k 6

277' STAllDBY STAT:DBY

.g.

1 83' STAllDBY STA!1DBY

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