ML17264A310

Responds to NRC 951211 RAI Re PTS Assessment for Plant Reactor Vessel

ML17264A310
Person / Time
Site:	Ginna
Issue date:	12/21/1995
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M93827, NUDOCS 9601020322
Download: ML17264A310 (25)

Text

CATEGORY j.

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDE)

ACCESSION NBR:9601020322 DOC.DATE: 95/12/21 NOTARIZED: NO DOCKET FACIL:60-.24A Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

SUBJECT:

Responds to NRC 951211 RAI re PTS assessment for plant reactor vessel.

DISTRIBUTION CODE:

A028D COPIES RECEIVED:LTR 1

ENCL J SIZE:

II TITLE: Generic Letter 92-01, Rev 1, Suppl 1 Responses (Reactor Vessel Struct NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 INTERNAL'ECIPIENT ID CODE/NAME PD1-1 PD CENTE OGC/HDS3 COPIES LTTR ENCL 1

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1 NOTE TO ALL "RIDS" RECIPIENTS:

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\\

AHD ROCHESIER GASANDEIECTRIC CORPORATION ~ 89 EASTAVENUE, ROCHESTER, N. Y IrI6d94001 AREA CODE 7I6 546-2700 ROBERT C. MECREDY Vice President Nvcleor Operotions December 21, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-1 Washington, D.C.

20555

Subject:

Response

to Request for Additional Information on Pressurized Thermal Shock (PTS)

Assessment for Ginna Reactor Vessel R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):

Letter from A.R. Johnson (NRC), to R.C.

Mecredy (RGE),

Subject:

R.E. Ginna Nuclear Power Station Request for Additional Information Pressurized Thermal Shock-(PTS)

Assessment for Ginna Reactor Vessel (TAC No.

M93827),

dated December 11, 1995.

Dear Mr. Johnson:

Rochester Gas and Electric Corporation has reviewed the referenced Request for Additional Information and provides the following responses:

Question l:

Since the initial reference temperature data for heat 62782 shows large variability (two values at 1'F and -38 F), provide the technical basis for not utilizing the generi c mean value and generic standard deviation for the initial reference temperature for B&W fabricated Linde 80 welds.

Note:

The square of the standard deviation for these values should have been determined by dividing the sum of the squares of the differences between the value and the mean value by n-2 to give an approximate unbiased estimate.

Response

RG&E proposes to revise the PTS submittal to use an initial reference temperature of -4.8'F and a

oz value of 19.7'F.

These values are supported by the RG&E Generic Letter 92-01 Revision 1

submittal dated July 2,

1992 as provided in BAW

1803, Revision 1 Table 3-3 which measured 34 data points.

The use of these values combined with the use of surveillance capsule data yields a margin term of 03000' (19.7)

+ (14)

= 48.3 F

(R.G. 1.99, Rev.

2) 7601020322 951221 PDR ADOCK 05000244 P

PDR

guesti'on 2:

Provide the unirradiated drop weight test data and charpy test data for welds material fabricated from heat number 62.782 weld wire.

Response

Question 3:

With the use of the initial reference temperature and standard deviation as discussed in 1.

above, the heat number 61782 unirradiated drop weight and charpy test data are no longer required.

Provide the actual chemi stry data utilized in determining the best-estimate chemistry for heat number 61782 welds and the chemi stry for the survei l lance welds.

Identify the source of the data and the reference document.

Hov vas the best-esti mate and the chemistry for the survei llance veld determined from this data?

Response

Question 4:

Attachment A provides a

discussion of the heat number 61782 and surveillance capsule weld SA 1036 chemistry.

Identify whether the survei llance data meets the credi bility criteria in Regulatory Guide

2. 99, Revision 2.

Demonstrate the criteri a 3 (scatter about the best-fi t line should normally be less than 28'F for welds) has been met by determining the scatter of the

>RTNDT from surveillance data about the best-fi t line described in Regulatory Position 2.l.

Does the correlation monitor material in the capsules fall within the scatter band of the data base for the material?

Response

Attachment B

provides a

discussion of the surveillance capsule credibility criteria.

Ver trul yo s,

Robert C.

Me redy REJ4412 xc:

Mr. Allen R. Johnson (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

~ r

Attachment A

Heat number 61782 chemistry (1)

Data used in heat number 61782 chemistry estimate:

The values of Cu and Ni used come from BAW 1500, pg. B-42 for welds SA 1036 and SA 1135 which are archive reactor vessel weldments for this material heat number.

A copy of the data table is provided as page (A-2).

(2)

The data values were used to determine a mean value of

.25 Cu and

.54 Ni per 10 CFR 50.61 guidance for best estimate of the mean of the values for the heat number of the material.

Using the chemistry factor tables of 10 CFR 50.61 yielded a chemistry factor of 167.6'F.

Surveillance capsule chemistry weld SA 1036:

(1)

For determining the chemistry factor value used in ratioing (Regulatory Guide 1.99, Rev.

2, position C.2),

available data for Cu and Ni chemistry were summed and mean values established.

The data came from WCAP 13902 Table 4-1 for tested capsules; BAW 1500 Exhibit. B-3 for archived weldment dropouts; and BAW 1500 page B-24 weld qualification report.

Hard copies of these data are provided as pages (A-3), (A-4), and (A-5).

P (2)

The above data values were summed together to yield mean values of

.214 Cu and

.505 Ni.

Using the chemistry factor tables of 10 CFR 50.61, the chemistry factor was determined to be 150.9'F

IfELO FILR NTRK FLUX SOURCE C

HN P

S SA 17bg 71249 '1 d

M

~ 590 i>46

~ 016

~ Of5 ST CR

~ 56

~ 150 NI

~ 63 HO

~ 36 CU

~ Z9 V

~ 005 AL.

TI CO CB TA

~ 014

~ ooi o 015

~ 00 4

~ 001 SH

~ 0)4 B

~ 001 PB AS ZR H

.004.C;r.COJ.Oic SA 1036 61162 ef rb 61112 61 712 cf 7'!2

": ~ SZ fI'hh f>t 712 f ltd?

el 712 el 7'I2 61782 6436NSDNSS3 5436'I lBNSS3 64 )etA atl SS 3 hC f>>>tc'l>IIISS>3 6CJ>> Nln;ISS3 84 Jfotc I'>O'l SC 36NBONSS I 6 C >Ftt 9 II!I.'a'5 l dC 36ttaat!SS 3

64 36>IQ0!t 153 bc if,tt)ONS93 6CJGIIBOIISSJ

~ 069

~ 563

~ 063

~ 561

~ CS3

~ ". 54

~ Qbf

~ Oct?

~ (95

~ 099

~ )91

~ 591 1 ~ 46 1 ~ 43 1 ~ 43 1 ~ 39 1 ~ C2 1 ~ 42 1 ~ I o 1 ~ 39 1 ~ I>>

1 ~Cl 1o42 1 ~ 40

~ 014

~ cl 14

~ 014

~ 013

~ (f3 F 013

~ 013

~ C1 1 o 013

~ 013

~ 61$

~ 011 F 006 F 006 F 006

~ Car

~ JCT

~ G') 7

~ Q)1

~ sCT

~ 001

~ 0 NI 7

. ~ 55 F 60

~ 51

~ 55

~ 54

~ 56 F 55

~ 53

~ 54

~ ri 4

~ 54

~ 57

~ 070

~ 070

~ 076

~ 050

~ 010

~ OTC

~ 0TC

~ 0'Ia

~ 09G

~ (90

~ Cha

~ 050

~ 49' 49

~ 49' I>9' 4h

~ 46

~ 49

.49

~ 50 c,9

~ 49-

~ 36

~ 36

~ 31

~ 35

~ 37

>37

~ 35

~ 39

~ 37

>37

~ 21

~ 2?

~ 24

~ 22

~ 23

~ 22

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.)e

~ ff>

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~ 15

~ 15

~ 010

~ 610

~ 510

~ CC9

~ (1(

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~ of' (1

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~ 0 id

~ 015

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~

15

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~ 017

~ 011

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~ rOJO ~ CCO

.003(.tca

~ it36 ~ 0CC

~ C020

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~ ((3C ~ (:C

>.03'sc

~ (G3C ~ JiC

~

0ZC ~ i-"0

. =f.zc.(.'a

~ CCJC

~

Co

~ OC 6 ~ COC

~ (020 ~ Oi(

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~ Otfa ~ 000

~ Ccc) ~ QCG

~ Cif0 ~i((

. 0)ea.c;0

~ Oi 10 ~ Cura

~ OCFO ~ 000

.Gaea'.0:(

~ OC15 ~ Ouo

~ oofa ~ C(6

~ 0060 ~ CCG

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~ 0)5

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~ 0)1 AC>>5 AC 1

~ ) ~ i

~ i)1 AC)'>>> ~ J

~ 555

~ 0)1

~ J)5

~ )1

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~ i) 1 F 069

~ Sof

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~ ifid

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~ >>cf

~ (21

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~ 62!

~ G?0 o(2C

~ GQ3

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~ 5 ~ 2

~ i>>

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~ i)2

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~f 11

~ 534

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~ 0? io AC?J

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I 6 l ~ 12 61712 f 1 7hZ el r12 ef 712 el t52 f.l 752

6) th?

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f.l 1 52 61 rh?

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~ 070

~ Jro

~ 070

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~ Cbo

>9TO

~ 055

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~ ')70

~ (10 o C 10

~ 57C F 010

.nro

~ C<0

~ Q70 F 99)

~ ') '90 a9c

.Qba F 065

~ 095 dada

~ fJC piro

~ )90

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~ 160 i>Cd 1 ~ Ch 1 ~ 46 1 oc>d 1 ~ Ce 1 ~ Co 1 ~ 47 i.ce 1 ~ cr 1 ~ 41 1 ~ 46 1 ~ 46 1 ~ Ch f ~ 46 1 ~ 49 1 ~ 4>>>

1 ~ 43 1 ~ 43 1 ~ 45 1 ~ 45 1 ~ Cc>

1 ~ 44 i.c a 1 ~ l4 1 ~ 41 1 ~ )h 1 ~ 43 1 ~ CJ 1 ~ 31

~ 013

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~ 015

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cce

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~ 35

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~ 41

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~ 27

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~ 565 AC(b o)(5

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ccei

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~ ((2 F 002

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~ 0 lb

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~ 1,!5

~ f. 1 5

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~ 070

~ 570

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~ 016

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~ Off>

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~ ri4

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~ 52

~ SC F 079

~ otr

~ 076

~ 077

~ C79 F 079

~ 59

~ 5'9

~ 59

~ 5d

~ 55

~ 59

~ 37

~ 37

~'ll

~ 31 AD )7

~ 31

~ 23

~ 23

~ 23

~ 24

~ 21

~ 22

~ Ccb

~ QC5

~ 0(5

~ 065

~ G(5

~ 055

~ C 10 009

~ 069

~ 009

~ J 10

~ oi)

~f02

~ 001

~ 002

~ 001

.aa?

~ Ot2

~ J)4

~ )14 o )14

~ (14

~ 014

~ QCC

~ OG4

~ 004

~ 004

~ CQC

~ 00>>

~ C12

~ 012

~ 612

.aif

~ 010 F 009

~ 0)3

~ )i3

~ Oac

~ 563

~ OG3

~ Oil 3

~ Jul o)oi

~ Q)1

.001

~ f>81

~ 051

.caz

~ )52

~ uaZ

~ Cs2

~ c >>2

~ 602

~ )>>7

~ 1st

~ Oil 1

~ C:6

~ 5)7

~ 0)1

~ (63

~ u(3

~ Ga)

~ )03 F 003

~ cl ~

~ 012

.a12

~ Gl)

~ Gfu

~ Gf6

~ G16 I

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A O

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4 ~

ibles 4-1 Ant cobalt TABLE4-1 Chemical Composition (wt%) of the R. E. Ginna Reactor Vessel Surveillance Materials"

. In i in the were re attained g points ained in Chemical Analysis (wt. %)

S Si Ni Cr Co Mo Cu Sn Lower Shell Forging 125P666 0.19 0.67 0.010 0.011 0.20 0.69, 0.37 0.013 0.57 0.02 0.05 0.004 0.01 Intermediate She11 Forging 125S255 0.18 0.66 0.010 0.007 0.23 0.69 0.33 0.015 0.58 0.02 0.07 0.003 0.01 0.075 (0.06) 1.31 (1.29) 0.012 (0.006) 0.016 (0 020)

O.S9 (0.41) o.s6~

(0.50)

O.S9 (0.03) o.ool

(--)

0.36 (0 22) o.ool

(--)

0.23 (0.22) 0.020

(--)

o.ols

(--)

Surveillance Weld'"

[a]

The values presented here are from References 2, 13 and 14.

[b)

The values in parenthesis are from an analysis performed on an irradiated Capsule T weld metal charpy specimen, W26 (Reference 2).

43

~ ~

H 1~

i{((0 f'ILR MIR(

SA 176~)

rf?49

~

TLI(X SDURCS 6738 M

C

~ 590 NN 1 ~ 48

(>>

~ 0th Si 015 SI

~ 56 CR

~ 150 NI

~ 63 t(0

~ 36 CU

~ 29 V

~ 005 AL.

?I CD

~ 014

~ 601 i C15 CB TA

~ 004

~ 001 SH

~ 0)4 8

~ ilo 1 PO

.OCC Act

.c;r ZR

~ C03 M

~ C14 SA.1036 0

61782 61152 6111Z f,l r12 Sf 112 f>>f?hh r>>I I 12 f 1 782 61?12 6( 112 61 rh?

ac 36H90HSS) 6436'I ICHSS3 84 3(>>tt)ANSS3 h4 ir>>tc'I>>It(S">>3 8 C!r" 3 D.'I c S 3 dc. I(.t: 3>>1W'3 bc 36WSDNSS3 6 C oeW9(t'.I!'>>S 3 64 36(((3AWSS 3 8 4 36'IA0 t( 1 5 3 643(.H)OH 1'S 3 84 Je(IBOI<SS)

~ 069

~ 563 F 083

~ '581

~ C53

~ "84

~ Qht

~ 0 ct?

o C95

~ 099

~ 591

~ 591 1 ~ 4&

1 ~43 1!43 1 ~ 39 1 ~ C2 1!42 t ~ Co 1 ~ 3'9 1 ~ Cu 1 ~ 41 1 ~ 42 1 !40

~ 014

~ 014

~ 014

~ 013

~ -'

3 F 013

~ 013

~ C1)

~ 013

~ 013

~ G 1$

~ 013 F 008

~ Cad

~ 008

~ 507 i i) C 7

~ 6'll

~ 0)?

F 507

~ Oal 0 (I?

- ~ 55

~ 60

~sl

,r!5

~ 54

.se ASS

~ 53

~ 54

~ 54

~ 54

~ 5?

.ara

~ 070

~ 076

~ 0 ho

~ CTO

~ 0?C

~ Q?C o O'IO

~ 090

<<9O

58O

~ 49

~ 49

~ 49

~ 46

~ Ch

~ 49

~ 49

~ 50

~ C9 i c>>9 AD )8 AD )8

~ 3T

~ 3h

~ )7

~ 3?

~ 3S F 39 i'll

~ 37

~ 21

~ 21

~ 24

~ 22

~ 23

~ 22

~ 21

. le

~ if>>

~ 17

~ 15

~ 15

~ 010

~ ala

~ 510

~ GC9

~ (1(

~ o 1!

~ Cl 1

~ 01:

~ (1

~ Oil

~ i. 1I

~ Ofr F 018

~ 015

,ote

~ 513

~ "15

~ )11

~ 0 ll

~ 0 1 1

~ Qfe

~ 6 1 7

~ 018

. o le e<<030.CCO

~ 003C AC(0

~ <<i(36 ~ OCC

~ C020

~ 0(C at(35 '.C

~ '0)CODS(

~ (G3C ~ JiC

~

02(: ~ Lsa

~ (f2( ~ L 0

~ L C3C ~ >>. CO

~ OC !0 ~ 6)C

~ (0 20 ~ QL(

.Cc? J.c(0

~ 6(65 ~ Oia

~ CC(aiaoa

~ Car) ~ 5CG

~(ifG ~ <<i(

>>>>)60 ~ <<>>Q

~ OL /0 ~ CGC

~ OC fa ~ Qoa

~ 6060

~0'(

~ OC la ~ Oua

~ 06fo AC(6 tao(oh(CG

~ 0<<6 F 005

~ 0)5

~ 0 5

~ Cuts

~ )

~ rr

~ C.45

~ Sis J hci

~ '5<<S

~ i)G i

~ 005

~0<<1

~ 081

~ CC1 o) 1

' )

L ~ 4

~ '1) 1

~ ')1 o i'll

~ JC9

~ )(1 i C(l

~ C.'.r

~ '

'SL5

~ C." 3

~i(6

~ L I>>

~ ') )9

~ Cod

~ J(6

~ (23

~ Oc2

~ Gcf

~ C20

~ u ~

~ I cf

~ Cit

~ v(9

~( (

~ 62(

!020

~ (ZC

~ 603 evo3

~ 003

>>5LZ

~ )03

~ L<<C

~')2

~ L I o(03

~ GGZ

~ 5ll

~ 048

~ 034 ea(1

~C':

~ Q? Lh

~ C? 3

~ v?i

~(3f

~ 0? 'i

~ (?1 SA 1135

~

~

SA 1.585 6(

~ 12 61112 el 112 61 182 61? 12 61182

(.1 712 f>>f? 82 6 1 7 o Lh 61?h?

61? hZ fit? 52 et ra?

61>>h?

61712 c f?12 et 7'!2.

6'h?

(.1 712 f,t ?h?

f.f 78?

61?SZ

~

61 782 r>>f ?62 61 782 61 78?

(.f 1<I?

61? 1?

61 18?

724< 5 7?c 45

?2445 12445 72(IS 72445 6 4 ri7t( 3 (IM SSC 1<cS?tc IA:ISSC 6451(t.lottcSC 64 r?W'ICWSSC PCS?N)riWSSC hc Sl'I'IAHSS<i 8 I 51'< A(!tt<< S4 nCr? tl(.t'!>>4 hurr7tt'IDWS

~ c>>

hCrrr't I>>!>>(Sou buS?w 3(;Hssc 845! >>!10!I.~ <<4 845?H'30!I S'SC 8491'IB OWSSC hc 5?ttlDH<<S4 5 4 5 7!<9AM iS I 6 4 sr i!lrtt".'.sc h 4 rr ? tt'35(t SS 4 84'57hl(IMSSC 6C r? IIROIISSC 845?t(RDI(cSC 84STII)AW Sc PCS? Wlo'IS<<S4 84<< rt<ACIISSC 8 4 rr 1( I:1IItI c 5 4 hv r 1 t(qWWSS 4 h45? ttl(IHSSc 84<<

~ I;ADIISSC 6C51!IRDIISS4 6991tt'!DHSS1 hrr 91>>tlDW",Sb f597t!AAttSSb 8597N30HSSS

?597WRDNSSa 859TNAOHSS8

~ 570

~ 070

~ 070

~ 076

~ Cda F 070

~ (8Q

~ 0?c

~ 'l la

~ Cra

~ C?D

~ 5?C

~ 070

~."70

~ &q>>I

.Qra

~ '!9<<

~ 'I90 Q9C

~ CSC

~ 085 095

~ Cdo

~ f IIC

~ frO

~ 390

~ 090

~ C90

~ 1CO

~ 070

~ 570

~ 01C

~ 510

~ oha

~ 060 1!48 1 ~ 48 1 ~ 46 1 ~ 44 1 ~ Cl l.ce 1 ~ Cl 1,47 1 ~ 46 1 ~ 48 1!45 1 ~ 48 1 ~ 49 1 ~ 43 1 !43 1 ~ 45 1 ~45 1 ~ Cc>>

1 ~ 44 1 ~ 40 1 ~ 44 1 ~ 4(

1 ~ 38 1 ~ 43 1 ~ 43 t ~ 31 1 ~ 44 1 ~ 45 1 ~ 43 1 ~ 43 1 ~ 43 1 ~ 4C

~ 013

~ Ot)

~ 013

~ 01Z

~ 013

~ 0 tc>>

~ 012

.ntZ

~ 012

~ C12

~ G12

~ 012

~ 011

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~ C(l F 012

~ 0 'L2

~ 511

~ 011

~ Qf 1

~ 015

~ C(0

~ 0 I a

~ 011

~ 010

~ 0 1)

~ 010

~ C09

~ 009

!a l6

~ 616

~ 0(6

~ 0 lfi

!016

~ C le

~ 013

~ 013

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~ 51'3

~ OL3

~ (13

~ 013 A (13

~ Ot3

~ 013

~ 013

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~ C 1.'I

~ 013

~ 013

~ (13

~.13

~ Ol '3

~ 513

~ 0'13

~ Cl) e 013

~ 01Z AC(3

~ 612

~ 012

~ C13

~ (12

!012 o Otr>>

~ C f f>>

~ 015

~ (16

~ G16

~ 016 5 o

~ s ci

~ 59

~ 51

~ 58 iea

~ 52

~ rr 1

~ SC

~ 5Z

~ 51

~ 52

~ 47 F 46

~ 46

~ cd

~ 51

~ Ch

~ cr

~ Ch

~ I 7

!45

~ 43

~ 46

~ 42

~ 44

~ C Ci

~ )h

~ 39 AS>

i<<re

~ rr 4

~ rr6

~ 52

~ 54

~ 067

~ 067

~ c 68

~ C r>>6

~ 0 f>> 6

0?a F 070

~ 0 lu

~ 570

~ Qrl F 074

~ 031

~ 070

~ 012

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~ 075

~ nha F 081 F 084

~ Clb

~ Chl

~ oal

~ 090

~ (94

~ f(C

~ 110

~ 096

~ 116

~ 130

. 07'3

~ Orl

~ i>> lf>>

~ 077

~ 6?9

~ 019

~ 58

~ 5>>I

~ 55

~ 58

~ 56

~ 58

~ 58

~ 58

~ 58

~ 5h

~ 59

~ 58

~ 5S

~ 5d

~ 59

~ 51 F 59

~ 56

~ 59 S9 S9

~ 59 lsd

~ (0

~ 66

~ 60

~ 59

.ea

~ 5'I S9

~ 59 S9

.sa

~ 58

~ 59

~ 36

~ 31

~ 37

~ 31

~ 31

~ 3?

~ 3?

~ 31

~ 3?

~ 38

~ 36

~ 36

~ 37

~ 37

~ 3S

~ )d

~ 'lS

~ 31

~ 39 o)h AD )9

~ 39 AD )9

~ 41

~ 41

~ 41 F 40

!41

~ '4 '1

.)r

~ 37

~ 31

!37

~ 37

~ 31

~ Zl AD )1

~ 31

~ 27

~ 27

~ 28

~ 29

~ 27

~ 29

~ 24

~ 25

~ ZZ

~ ?Z

~ lf

~ 32

~ 31

~ 34

~ '3C

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~ 26

!22

!ZZ

!23

~ 21

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~ 17

~ 23

!23

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~ ZZ

.acs iu(5

~ ((5

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.o(s

Q.s

~ JC5

!G(5

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~ 5(5 o C(cr

~ J(5

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!066

~ I'>> 6 ac(e

!C(6 ooe?

AC(h

~ i69

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1

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I<<r

~

Lh

~ 0')7

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57

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~ Ood

~ 05$

F 067 F 006 i ')Qd

!OC9

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F 059

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~ G(S

~ 005

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~ OC5

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~ 0(5, ~ 069

ofs :ao9

.aat

~ 502

~ 652

~ C02

~ (02

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~ 502

~ (C2

~ 002

~ G02

~ 602

~ (02

~ (02

~ 002

~ CC2

~ C02

~ C.O 2

.noZ

~ 602

~ (02

~ 052

~ (02

~ (02

~ (02

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~ GOZ

~ CO?

i((2

~ G02

~ VOZ

~ 001

~ 002 iaaf

~ 002

~ OCZ

~ 016

~ 017

~ 011

~ 011

~ 0 17

~ all

~ 017

~ 617

~ (1T

~ Cfb

~ C lb

~ 012

~ J17

~ (17

~ C lr

~ <<11

~ <<16

~ Ofd

~ 6 th

~ Clb

~ G fr

~ 011

~ 617

~ 0 16

~ 0 16 F 018

~ Qfb

~ Ofb

~ )f?

~ J14

~ )14

~ 014

. a14

~ (14

~ 014

.Cac

~ 0(5

~((5

~ OC9

~ 564

.act

~ QQS

~ 06<

~ 0(C

~ Oar

~ CC5

!OGS

~ C05

~ 0(5

~ G(5

~ C(c

~ 00

~ 005

~c(5

~ OC5

~ 005

~ DC4 AC(5

~ 005 F 005

~ SCC

~ CC5

~ 605

~ OCC

~ 064

~ 004

~ 004

~ CCC

~ 005 F 013

~ 11)1

~ <<8

. cia

~ )is

~ 0th AC(b

~ Cob

~ OL?

~ ((9

~ (<<9

~ Gla

~ 511

~ 01G

~ C14

~ r14 F 866

~ 0(6

~ (53

~ Qh.Z F 002 AD<<5

~ CL?

~ G(9 F 007

~ Car

~ Ccb

~ 0(T

~ C12

~ 012

~ G12

~ 0 1(>>

~ 010 F 509

~ ')(2

~ 5V

~ L.3

~ QJZ

~ 803

~ 0(3

~ 063 Q!>> 3

~ 503

.053

~ QC3

~ OL3 F 052

~ CG2

~ QG3

~ ZG3

~ ))3 F 053

~ 503

~ u(3

~ DG3

~ ilC 3

~ 003

~ 3:3

~ 'i)4

~ <<03

~ 003

~ Cu)

~ 5>>34

~ ih) 3

~ )<<3

~ OGC

~ QGS

~ 063

~ 00,3

~ 051

~ Ojf

~ 441

~ v)L

.051

fit

~ Ool

~ ))t

~ 0<<1

~ O<<1

~ <<<<1

~ G)1

~ Gvi

~ 5C1

~Gii

~ <<il

~ 0",L

~ Ct<<l

~ 5<<'1

~ i') 1

~ (<<1

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~ 0". 1

~ 6>>', 1 ar 1

~ Ci', L

~ Qi. ~

~ oui

>>Oui

~ J:1

~ 031

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~ Gal

~ 051

~ QC1

~i()

~ (61 F 001

~ (CZ

~ <<C2

~ J)2

~ Joh 2

~ J(2

~ rr C2

~ UV2

~ <<JZ

~ )02 C)2

~ CJZ

~ CC1

~ (CZ

~ 0)2

~ L52

~ ii)2

~ )(2

~ daf

!CO2

~ 352

~ vGZ F 642

~ LU2

~ GOZ

~ ((S

~ 6th

~(,9

~ 6 eh

~ ('9

~ C)d

~ 0 ib

~ 0)S

~ 5'6

~ 616

~ CJS

~ G ~ I>>

.0 e

~ (01

~ 4<<5

~ C <<6

~ <<u

~ ))7

~ U<<6

~ <<'.7

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~ GL4

~ C lr

.r e

i),l

~ (j9

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.6)e

~ 3 7

~..<<1 F 007

~ C 8

~ 0)l

~ 0)1

~ )03

~

~ (04

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~ 6<<4

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~ Liu 3

~ 6(4 F 403

~ <<I 6 h 'I

~ u ~

~ hG3

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~ (6

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~

oui)

~ QGC 1

~

u

~ i V

~ -CC 6 a.'

(JC

~ Lu V

~ (CC

~ '04 AC(4

~ <<QC

~ CG3

~ v(3

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~ 003

~ 003

~ 064

~ 012

~ j(5

~ufs o 01<>>

~ 016

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~Ctl

~ 6th

~ 0

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~ 615

~ (19

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air<<

~ 0 la

.017

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Listed belo!r is the heat of '.~i=e ard type of flux used ard the results o

ti'ese tests.

i/8 d" a.

Page lz.'-i!o-l~i,:-.t-Vo. 61782 S'-

e o" ';leid Pad:

4" z o" z '-1/2" high

)velding Conditions:

A.C.) "50 Alps, 30 Volts 10

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B-24 Si.".!on

Attachment B

Evaluation of the R.E.

Ginna Reactor Vessel Surveillance Data Credibility INTRODUCTION:

Regulatory Guide 1.99, Revision 2,

describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels.

Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data.

The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been four surveillance capsules removed from the R.E.. Ginna reactor vessel.

To use these surveillance data sets, they must be shown to be credible.

In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the R.E.

Ginna reactor vessel surveillance data and determine if the R.E.

Ginna surveillance data is credible.

EVALUATION:

Criterion 1:

Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G

to 10 CFR Part 50, "Fracture Toughness Requirements,"

May 27, 1983 to be:

"the reactor vessel (shell material including welds, heat affected

zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."

The R.E.

Ginna reactor vessel consists of the following beltline region materials:

a)

Intermediate shell forging heat number

125S255,

b)

Lower shell forging heat

125P666, and c)

Intermediate to lower shell circumferential weld seam SA-847 (fabricated with 1/8 inch Mn-Mo-Ni weld fillerwire, heat number 61782 and Linde 80 flux, lot number 8350).

The R.E.

Ginna surveillance program utilizes test specimens from both the intermediate and lower shell forgings.

The weldment used in the surveillance program was fabricated with 1/8 inch Mn-Mo-Ni weld filler wire, heat number 61782 and Linde 80 flux, lot number 8436.

Since, all beltline materials are contained in the surveillance program of the R.E. Ginna reactor vessel, the limiting material is contained in the surveillance program.

Hence, the R.E.

Ginna reactor vessel surveillance program meets this criteria.

Criterion 2:

Scatter in the plots Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.

Plots of Charpy energy versus temperature for the unirradiated condition are presented in WCAP-7254, "Rochester Gas and Electric Robert E. Ginna Unit No.'

Reactor Vessel Radiation Surveillance Program," dated May 1969.

Plots of Charpy energy versus temperature for the irradiated condition are presented in:

~

Westinghouse Report FP-RA-1, "Analysis of Capsule V from the Rochester Gas and Electric R.E.

Ginna Unit No.

1 Reactor Vessel Radiation Surveillance Program,"

dated April 1973,

~

WCAP-8421, "Analysis of Capsule R from the Rochester Gas and Electric Corporation R.E.

Ginna Unit No.

1 Reactor Vessel Radiation Surveillance Program,"

dated November 1974/

~

WCAP-10086, "Analysis of Capsule T from the Rochester Gas and Electric Corporation R.E. Ginna Nuclear Plant Reactor Vessel Radiation Surveillance Program," dated April 1982, and

~

WCAP-13902, "Analysis of Capsule S from the Rochester Gas and Electric Corporation R.E.

Ginna Unit Reactor Vessel Radiation Surveillance Program," dated April 1993.

The scatter in the data presented in these plots was small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy of the R.E.

Ginna surveillance materials unambiguously.

Therefore, the R.E.

Ginna

surveillance program meets this criterion.

Criterion 3:

When there are two or more sets of surveillance data from one reactor, the scatter of ~RT>>~ values about a

best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28'F for welds and 17'F for base metal.

Even if the fluence range is 'large (two or more orders of magnitude),

the scatter should not exceed twice those values.

Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82.

The least squares method as described in Regulatory Guide 1.99, Revision 2 will be utilized to determine a best-fit line for that data and to determine if the scatter of these

~RTNpy values about this line in less than 28'F for welds and less than 17 F for the plate.

Following is the calculation of the best fit line as described in Regulatory Guide 1.99, Revision 2.

(B-3)

TABLE 1 Ginna Surveillance Capsule Data Material Lower Shell Forging 125P666 (Tangential)

Intermediate Shell Forging 125S255 (Tangential)

Weld Metal Capsule R

F(1) 0.556

l. 15 1.97 3.87 0.556

1. 15 1.97 3.87 i~ 1 0.556 1.15 1.97 3.87 i~1 FF(2)

(x) 0.836

1. 039

1. 185

1. 349 4.409 0.836

1. 039 1.185

1. 349

4. 409 0.836

1. 039 1.185 1.349 4.409 hRTNDT(3)

(y) 25 25 30 42 122 60 60 140 165 150 205 660 FFKa,RTNDT (Xy) 20.9 26.0 35.6 56.7 139.2 80.9 80.9 117.0 171.4 177.8 276.5 742.7 FF'x')

0.699 1.080 1'04 1.820 5.003 0.699 1.080 1.404 1.820 5.003 0.699 1.080 1.404 1.820 5.003 (1)

F = Fluence (10 n/cm, E ) 1.0 MeV)

(2)

FF = Fluence Factor

= F' (3)

~RTND>

values do not include the adjustment ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1, since the surveillance capsule materials are equivalent to the actual beltline materials Per the 27th Edition of the CRC Standard Mathematical Tables (page 497), for a straight line fit by the method of least squares, the values b, and bi are obtained by solving the normal equations nbp + bi Exi = Eyi and bpExi + biZxi

= EXiyi

These equations can be re-written as follows (b~ = a and b~ = b):

n n

Zy< = an + bEx<

and i=1 i=1 n

n n

Ex,y, = aEx,

+

bEx,'=1 i=1 i=1 Lower Shell For in 125P666:

Based on the data provided in Table 1 these equations become:

122 = 4a t 4.409b and 139.2

= 4.409a

+ 5.003b

Thus, b

= 33.004 and a

= -5.879, and the equation of the straight line which provides the best fit in the sense of least squares is:

Y

= 33.004 (X) -5.879 The scatter in predicting a value Y corresponding to a given X

value is:

e = Y - Y TABLE 2 Lower Shell Forging 125P666 FF 0.836

1. 039 1.185 1.349 hRTNDg (30 ft-lb)

('F) 25 25 30 42 Best Fit hRTNDg

('F) 21.7 28.4 33.2 38.6 Scatter of hRTNDg

('F) 3.3

-3.4 3 ~ 2 3.4 The scatter of

~RT>>~

values about a best-fit line drawn as described in Regulatory Position 2.1 (Table

2) is less than 17'F.

Therefore, this criteria is met for the surveillance data of lower shell forging 125P666.

Intermediate Shell For in 125S255:

Based on the data provided in Table 1 the equations become:

60 = 4a

+ 4.409b and 80.9

= 4.409a

+ 5.003b

Thus, b = 103.122 and

a. = -98.666, and the equation of'he straight line which provides the best fit in the sense of least squares is:

Y

= 103.122 (X) -98.666 The scatter in predicting a value Y corresponding to a given X value is:

e = Y - Y TABLE 3 Intermediate Shell Forging 125S255 FF 0.836 1.039 1.185 1.349

>RTNDx (30 ft-lb)

( F) 60 Best Fit hRTNgg

( F)

-12.5 8.5 23.5 40.4 Scatter of hRTNpy

('F)

12. 5

-8. 5

-23.5 19.6 The scatter of

~RTND~ values about a best-fit line drawn as described in Regulatory Position 2.1 (Table

3) is less than 34'F (2 x 17'F).

Therefore, this criteria is met for the surveillance data of intermediate shell forging 125S255.

Weld Metal:

Based on the data provided in Table 1 the equations become:

660 = 4a

+ 4.409b and 742.7

= 4.409a

+ 5.003b

Thus, b = 106.265 and a

= 47.869, and the equation of the straight line which provides the best fit in the sense of least squares is:

Y

= 106.265 (X) + 47.869 The scatter in predicting a value Y corresponding to a given X value is:

e = Y - Y TABLE 4 Surveillance Weld Metal FF 0.

836'.039 1.185 1.349 hRTNDg (30 ft-lb)

('F) 140 165 150 205 Best Fit hRTNpg

('F) 136. 7 158.3

'173. 8 191. 2 Scatter of dRTNDg

('F) 3.3 6.7

-23.8 13 '

The scatter of ~RT>>> values about a best-fit line drawn as described in Regulatory Position 2.1 (Table

4) is less than 28'F.

Therefore, this criteria is met for the surveillance data of the circumferential weld material.

Criterion 4:

The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +25'F.

The capsule specimens are located in the reactor between the core barrel and the vessel wall and are positioned opposite the center of the core.

The test capsules are in baskets attached to the thermal shield.

The location of the specimens with respect to the reactor vessel beltline provides assurance that'he reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25DF.

Criterion 5:

The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material.

The correlation monitor material SA302 Grade B utilized in the R.E.

Ginna surveillance program was furnished by the U.S.

Steel Corporation through'ubcommittee II of ASTM Committee E10 on Radioisotopes and Radiation Effects.

A plot of the Measured Shift minus the Regulatory Guide 1.99, Revision 2, shift was obtained from the Oak Ridge National Laboratory and is described on page B-9 and B-10 of this attachment.

The plot shows the Ginna data as solid points.

The data has been shifted such that the Mean Value is at zero and the two-sigma bound at 25'F. All the Ginna surveillance correlation monitor material data fall within the two-sigma bounds (scatter band) of the SA302 Grade B data per the criterion as described by the CPED transmittal of page 'B-9.

CONCLUSION:

Based on the preceding positive responses to all five criteria of Regulatory Guide 1.99, Revision 2,

Section B, the R.E.

Ginna surveillance data is credible.

(B-8)

0

DEC 15 '95 12:KA'II'NAtYSIS SEC, 6155749619 P.1/2 OAKRIDGE NATIONALLABORATORY Computational Physics & Engmeering (CPED)

NucIear Analysis 4, Shielding Section Facsimile Transmittal TO:

Hd Tele PAX NO. (412) SV+6SSV VEBZFYNO.

OPHCB NO.

PROM:

Joe Pace FAXNO. (423) S74-9619 VIHGFYNO. (423) 576-1610 OPPICE NO.

COMMENTS: An additional plot has been gcncrated and shows the Ginna data as a solid symbol. Moreover, the data has been sMScd such that the Mean Value is at zero and thc tw~igma bound at 2S degrees F. Allthe Ginna surveillance CMMdata foal withinthe R.G.

1.99 two-sigma bounds.

THIS TRANSMITTALCONSIST OP~PAGES (EXCLUDINGCOVER SHEET)

DATE: December 15, 1995 TQdE:

11;30

Residual vs Fast Fluence for A3028 ASTM Correfation Monitor Materials from Westinghouse Reported Data (wla Yankee Rowe) 40

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Ginna Plant Data 0

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-20 00 o

-30

, -40 Fluence, E > 1 MeV [nlcrn']

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