ML18100B225

Forwards Results of Util Recalculation of Initial Rtntd Values & Basis for Calculations,In Response to GL 92-01, Reactor Pressure Vessel Structural Integrity.

ML18100B225
Person / Time
Site:	Salem
Issue date:	07/20/1994
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NLR-N94123, NUDOCS 9407280249
Download: ML18100B225 (11)

Text

'.

, ' " ,' ' Public Service

":> ' , Electric and Gas

• - "-~ ~-- Company Stanley LaBruna Public Service Electric and Ga/company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering JUL 2 ©1994 NLR-N94123 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

GENERIC LETTER 92 REACTOR PRESSURE VESSEL STRUCTURAL INTEGRITY, SUPPLEMENTAL RESPONSE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated April 21, 1994, the NRC requested PSE&G to review specific reactor pressure vessel summary data files developed by the NRC as part of the Generic Letter 92-01, Reactor Vessel Structural Integrity program. During this review by PSE&G, Initial RTNDT values listed by the NRC were different than previously submitted by PSE&G for several reactor pressure vessel materials. As a result of these differences, it was agreed that Public Service Electric & Gas Company (PSE&G) would recalculate the Initial RTNDT values for Salem Units 1 and 2, and provide this data to the NRC along with the relevant assumptions and methodology that were used for the calculations. (See PSE&G letter to the NRC dated June 20, 1994 (NLR-N94114).) Attachment 1 to this letter provides the results of PSE&G's recalculation of the Initial RTNDT values and the basis for these calculations.

In addition, the value of the Initial RTNDT for axial weld 2-442 should be -56 degrees F rather than the -40 degrees F provided in the NRC summary data files. The actual Charpy curves for weld 2-442 are not available, and the generic value of -56 degrees F should be used in accordance with 10CFR50.61. Thus, the Initial RTNDT values for the three Unit 1 and three Unit 2 beltline welds should all be -56 degrees F.

Also, the Salem Unit 2 summary data file for Upper Shelf Energy (USE) reflected a value of 66 ft-lbs for the shell plate B4712-2 1/4T USE at End-of-Life (EOL). Our response dated June 20, 1994 (NLR-N94114) provided a revised value of 82 ft-lbs. This value should be changed to 81 ft-lbs.

JUL201994*

Document Control Desk 2 NLR-N94123 is a hand corrected set of the summary data files provided to PSE&G in the NRC Letter dated April 21, 1994. The attached summary data files consolidate the changes discussed above and the changes previously provided to the NRC in PSE&G Letter NLR-N94114 dated June 20, 1994.

If there are any questions relative to the information provided herein, please feel free to contact us.

Attachments (2)

Affidavit c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem

u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

REF: NLR-N94123 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM

s. LaBruna, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.

KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires on My Commission Expires April 21, 1998

"NLR-N94123 ATTACHMENT 1 SALEM 1 SHELL PLATE IRTNDT VALUES The IRTNDT values for the six beltline shell plates were determined using drop weight data and Charpy data. The Charpy data for three of the plates was obtained using transverse Charpy specimens. These three plates are B2402-l, B2402-2, and B2402-3. The methodology used was as described in Branch Technical Position MTEB 5-2, "Fracture Toughness Requirements". Specifically, the larger of the 50 ft-lbs energy value and the 35 mil lateral expansion value was determined for each plate. Next, 60°F was subtracted from the larger value. This resultant number was then compared to the drop weight value. The IRTNDT was then determined as being the higher of the resultant number and the drop weight value.

The Charpy data for the other three beltline plates was obtained using longitudinal Charpy specimens. These three plates are B2403-l, B2403-2 and B2403-3. The methodology used was as described in Branch Technical Position MTEB 5-2, "Fracture Toughness Requirements". Specifically, the larger of the 50 ft-lbs energy value plus 20°F and the 35 mil lateral expansion value plus 20°F were determined for each plate.

Next, 60°F was subtracted from the larger of the two values.

This resultant number was compared to the drop weight value.

The IRTNDT was then determined as being the higher of the resultant number and the drop weight value.

A summary of the drop weight and IRTNDT values for all six Salem 1 plates is given below. Note that the IRTNDT value for B2402-3 is -3°F as listed below, not -23°F as previously reported in 1993.

SALEM 1 DROP WEIGHT AND IRTNDT VALUES PLATE NDTT, OF IRTNDT, OF B2402-l -30 45 B2402-2 -30 -5 B2402-3 -40 -3 B2403-l -40 4 B2403-2 -70 18 B2403-3 -40 6 Page 1 of 2

NLR-N94123 ATTACHMENT 1 {Cont'd)

'SALEM 2 SHELL PLATE IRTNDT VALUES The IRTNDT values for the six .beltline shell plates were determined using drop weight data and Charpy data. The Charpy data for the six plates was obtained using transverse Charpy specimens. The methodology used was as described in Branch Technical Position MTEB 5-2., "Fracture Toughness Requirements". Specifically, the larger of the 50 ft-lbs energy value and the 35 mil lateral expansion value was determined for each plate. Next,** 60°F was subtracted from the larger value. This resultant number was compared to the drop weight value. The IRTNDT was then determined as being the higher of the resultant number and the drop weight temperature. A summary of the drop weight and IRTNDT values for the six Salem 2 plates is given below.

SALEM 2 DROP WEIGHT AND IRTNDT VALUES PLATE NDTT, OF IRTNDT, OF B4712-1 0 0 B4712-2 -20 12 B4712-3 -50 10 B4713-1 -10 8 B4713-2 -20 8 B4713-3 -10 10 Page 2 of 2

8 Sunvnary File for Pressurized Thermal Shock Plant 8eltline Heat No. ID Neut.  !RT..,. Method of Chenti stry Method of XCu Xiii Name !dent'. !dent. Fluenee at Detemin. Factor Deten1in.

EOL/EFPY !RT- CF Salem 1 Int. shell 82402-1 C* 1354-1 '.38ETV' q 1,&.f")..E I r(t}5f: Plant Snmcific 157.82 Calculated 0.24 0.53

~F

~~'7 EOL: Int. shell C-1354-2 1.w1r 11 o Pl wit 154.37 Calculated 0.53 8/13/2016 82402-2 1.~?.Elt> -SF s-t:ffic Int. Shell 82402-3 C-1397-2 .~_.w,q 1f' -':JF Pl wit s-fftc 115.53 Calculated 0.22 0.51

~Lf~F Lower c-1356-1 .... ]51!19 MTE8 5-2 128.8 Table . 0.19 0.48 Shell 1.3'1Elq 82403-1

~3~F Lower C-1356-2 -4 .35E!19" MTEB 5-2 129.9 Table 0.19 0.49 Shell 1, 3 I£ J ll 82403-2 Lower C-1356-3 1.35E,9' ;YF 9 MTE8 5-2 128.8 Table 0.19 0.48 Shell 82403-3 1.3'11?19 6°F Int. Shell 398196 & ~ *56°F G-ric 214 Table 0.18 1.00 Axial 348009 Welds (T) 1.13£ 1q 2-042 Int. to 13253 _J...liE19"" -56°F Generic 195.8 Table 0.25 o.n Lower Shell ,. '39-19 Circ. Weld 9-042 Lower Shell 348009 ~ -56°~ Generic 220 Table 0.19 1.00 Axial 1.3'1Ell)

Welds 3-042 References for Salem 1 Material type and data other than that noted below was provided in the J~ 30, 1992 letter frOll S.E. Miltenberger (PSEMi) to USNRC Doct.aent Control Desk, *Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54(f), Salem Generating Station Unit Noa. 1 and 2.

Chmfstries for the tntermdf ate shell course platn were provf~ in the August 4, 1993 letter S. LaBnni to USNRC DocUlllf'lt Control D..k, *Response to Generic Letter 92*01, Revision 1 Retietor Vessel Structural Integrity, 10CFR50.5054(f) Request for Addftfonal lnfof'lletfon, Sal .. Generating Statton Unit Na.. 1 and 2.

Initial RT- and WSE values for the beltltne plates were provided in the Sept911ber 29, 1993 letter frm s. Lallruna to USNRC DOCUlllf'lt Control Desk, *SUppl--.tal Response to Generic 92-01, Revision 1 Reactor Vnael Structural Integrity, 10CFR50.54(f) Request for Addittcn11l lnforlll!ltfon, Sall!ll Generating Statton Unit No. 1.

Fluence reported in a December 15, 1992 letter frOll s. La8na18 (PSE&G> to USNRC.

8 Staff determination of IRTNDT from transverse CVN data.

9 Staft determination of IRT 1 frc~ longitudinal CVN data by converting longitudinal data to transverse ~ata using the 65% correction factor, in accordance with MTEB 5-2.

PAG£ 2. CF la 1"-<e" i ~eJ ( /13 Jc'.JL/ 9 Summary File for Pressurized Thermal Shock Plant Bel tline Heat No. ID NeYt. 1itT_ Method of Che11istry Method of XCu Xiii Name ldent. Ident. Fluence at Detern1in. Factor Deten1in.

EOL/EFPY IRT- CF .

Salem 2 Int. Shell B4712*1 C*4173*1 +.38El9 q l*S~EI v( ~of MTEB 5*2 89.8 Table 0.13 0.56 EOL: Int. Shell C*4186*2 t.m1cr 12*F Pt ant ~1.6'"' Calculated 0.12 0.62 4/18/2020 B4712*2 1,52.Gl'f Snecific 118.15 Int. Shell B4712*3 C*4194*2 1.38e19

• • S'::l I! 19 rf 1~°F MTEB 5*2 73.7 Table 0.11 0.57 Lower Shell C-4182*1 .J..lrt!19 '1 I MTEB 5~2 83 Table 0.12 0.60 14713*1 1.'i"t E 1q . 8°F Lower C-4182*2 -1 *.r, U!'t9' p'F I MTEB 5*2 82.4 Table 0.12 0.57 Shell Bt>F B4713*2 I 1'-l'i ti 9 Lower B-8343*1 +.41!1t -p4 I MTEB 5*2 82.6 Table 0.12 0.58 Shell B4713*3 1.Lf't Et9 ID°F Int. Shell Axial 13253 &

20291 en L95E19'

~ Plant Specific

~ ~ed 0.23 0.73

,,, ., 121q Welds 2*442 Lower 21935 & L911:~9

-5b°F

• 56°F Generic 202.7 T o.loJe.

Table 0.20 0.86 Shell 12008 CT)

AXial 1. lS E 1q Welds 3*442 Int. to 90099 .. *--*r

---*- *56*f Gereric* 95 Table 0.18 0.20 Lower Shell 1.Li"\Elq Clrc. Weld 9*442 References for Salem ~

Material type, initial RT 111, and data other than that noted below was provided in the June 30, 1992 letter S.E.

Miltenberger (PSE'6> to USNRC Docunent Control Desk, HResponse to Generic Letter 92*01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54Cf), Sale11 Generating Station Units Nos. 1 and 2.

The chemistry for plate B4712*2 was provided in the August 4, 1993 letter frOll s. La&,,.,. to USNRC Docunent Control Desk, "Response to Generic Letter 92*01, Rr1iaion 1 Reactor Vessel Structural Integrity, 10CFR50.54(f) Request for Additional lnformtion, Salm G<<wratfng Station Unit N09. 1 and 2.

Fluence reported tn a Decemer 15, 1992 letter from s. Lalln.. (PSE&G) to USNRC.

9Staff determination of IRT T from longitudinal CVN data by converting longitudinal data to transverse "8ata using the 65% correction factor, in accordance with MTEB 5-2.

ENCLOSURE 2 8 Sunvnary File for Upper Shelf Energy Plant N11111e 8eltline HHt No. Material 1/4T USE 1/4r" Unirrad. Method of

!dent. Type at Neutron US'E

. Detttrmin.

' EOL/Ef PY Fluence at unirrad.

EOL/EFPY USE Salem 1 Int. shell C-1354-1 A5338*1 70 '9;tt19 91 Direct 8<!402-1 81.S'EIS EOL: Int. shell C* 1354*2 A5338*1 83 .a.21!1s- B 98 Direct 8/13/2016 82402-2 g.5.:1

~88 Int. Shell C-1397-2 104 Direct

~:W~ r'S A533B-1 82402*3 Lower Shell C-1356-1 A5338*1 68 -*-

...-*--*- 93 - 65X 82403-1 8.'Z. EIS Lower C-1356-2 A5338*1 6i 8.6!18"' 83 65X Shell 82403-2 8."l.EIB Lower C-1356-3 A533B* 1 62 .8 Qli18 85 65X Shell 82403-3 S.2.E18 Int. Shell 398196 & Linde 53 -6.6E~8 75 NRC Axial 348009 (T) 1092, SAii Generk Welds b:7E18 2-042 Int. to 13253 Linde 69 ~ 111 surv.

Lower 1092, SAii Weld Shell Circ. Weld 8.'3E1B 9-042 Lower 348009 Linde 75 -&.9EHt-* 112 Sister Shell 1092, SAii Plant Axial Welds

8. 2 EI~

3-042

• g

• Sumrn~ry File for Uppt:r* Shelf Energy Plant Name Beltline Heat No. Material 1/4T USE 1/4T Unirrad. Method of

!dent. Type at Neutron USE Determin.

EOL/EFPY Fluence at Unirrad.

EOL/EFPY USE Reference for Salem 1 Material type and data other then th*t noted below was provided in the J~ 30, 1992 letter s.E. Miltenberger CPSE&G> to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structural Integrity, 10CFR50.54Cf), Salem Genereting Station Unit Nos. 1 and 2.

Chemistries for the intenlediete shell course pletea were provided in the August 4, 1993 letter from S. LaBn.w to USNRC DOC\mlnt Control o..k, *Reaponse to Generic Letter 92-01, Revision 1 Reactor Vessel Structurel Integrity, 10CFR50.54Cf> Request for Additional Information, Selem Generating Station Unit Noa. 1 8nd 2.

Initial RT,., and WSE values for the beltline plates were provided in the Septed>er 29, 1993 letter fra11 s. Las~ to USNRC Docunent Control Desk, "Supplemental Response to Generic Letter 92*01, Revision 1 Re*ctor Vessel Structural Integrity, 10CFR50.54Cf) Request for Addition8l Information, Salem Generating Station Unit No. 1.

UUSE values for the beltline welds except int. shell axial welds 2-042, were provided in the Deceri>er...Jr;""1993 letter frClll S. LaBrU'W to USNRC Docunent Control Desk, "Response to Generic Letter 92-01, Revision 1 Reactor Vessel Structur*l Integrity, ,10CFRS0.54Cf) Request for Additional Information, S*l .. Genereting Station Unit Nos. 1 and 2.

UUSE value for int. shell axiel welds 2-042 is a generic velue for welds fabricated by Coriluation Engineering using Linde 1092, 0091, 123 and Arcos B-5 fluxes (Ref. Letter fra11 S.

BlOOlll CUSNRC) to T. L. Patterson COPPO) dated Decenmer 3, 1993.

Fluence blised on data provided in a Decenmer 15, 1992 Letter fr0111 s. LaS~ CPSE&G) to USNRC.

-10

• SJrnmary File for Upper Shelf Energy e \)PJGIS .5 o F ta Rev.*sed '7/r ~/q!.f Plant Name 8eltl ine Heat No. Material 1/4T USE 1/4T Unirrad. Method of

!dent. Type at Neut-ron USE Detennin.

EOL/EFPY Fluence at - Unirrad.

EOL/EF?Y USE Salem 2 Int. Shell 84712-1 C-4173-1 A 5338-1 Ji' BL/ ~Bq,a GI _w,ob ~i~ee-t EOL:

4f 1'a/2020 Int. Shell 84712-2 C-4186-2 A 5338-1 Ji6 81 q. IE' I 8

-&=tt1! JY q7 ..65%"

o; .. ec:t-1_

Int. Shell 84712-3 C-4194-2 A 5338*1 t£ 8 t., -8oie18'

q. IE= I B JY107 ~

Diret. t Lower Shell 84713-1 C-4182*1 A 5338-1

~IS ~

8.6El8

~ qg

~

D*v-e c. t-Lower C-4182-2 A 5338-1

~S:J. ..8.4E-il ,.,, 6R"""

Shell 84713-2 8.6E 1g ro 3 o~ re(. t-Lower 8-8343-1

~~I A 5338-1 Shell ,6 q'"] ~ .651--

84713-3 8.6E18 O : ... ed:

Int. Shell 13253 & Linde ~9 '"*18 96 9 Generic Axial 20291 (T) 1092, SAW Welds 63 '7,0 Et8 2-442 Lower 21935 & Linde -rs-. ~ 114 Sister Shell 12008 (T) 1092, SAW Plant Axial Welds 18 r-r~o EIB 3-442 Int. to 90099 Linde 52 ~.i!E18 75 NRC Lower 0091, SAW Generic Shell Circ. Weld e.GE 18 9-442 6

Licensee utilized a generic UUSE value; additional information required to confirm the value.

11

• Su11111ary File for Upper Shelf Energy Plant Name Beltline Heat No.

• M11teri al 1/4T USE 1/4l Unirracl. Method of ldent. Type at Neutron USE Detenain.

t:C-./EFPY Fluence at Unirrad.

EOL/EFPY USE Reference for Salem 2 Material type, Initial RT..,, and data otl.er than that noted below w.s provided in the J~ 30, 1992 letter S.E. *Miltenberger CPSE&G) to USNRC DOCUlll'lt Control Deak, MRespona* to Generic Letter 92*01, Revision 1 Reactor Vessel Structur1l Integrity, 10CFR50.54Cf), Sll1111 Generating Station Unit Nos. 1 Ind 2.

The chemistry for pl1te 84712*2 wa1 providld in the August 4, 1993 letter from s. LeBrum to USNRC. Doc~t Control Deak, *Response to Generic Letter 92*01, 'Revision 1 Ructor Vnael Structur1l Integrity, 10CFR50.54(f) Request for AddltiOl'llll lnfol'lllltion, S1l1111 Generating st1tion unit Nos. 1 and 2. ~ece~l,tv ~ >1qt.,;> >(

WSE value for the bel tl ine welds except for 9*442 were provided in the Dec1mnr 4, 1993 letter frOll s. La8r1n1 to USNRC Doclment Control Dffk, 0 R1aponae to Generic Letter 92*01, Revision 1 Reactor Vessel Structure Integrity, 10CFR50.54Cf) Request for Additional lnfon111tion, Salem Generating Station Uriit Noa. 1 and 2.

WSE values for weld 9*442 is a generic value for welds fabricated by Cadlustion Engineering using Linde 1092, 0091, 123 and Arcoa B-5 fluxes (Ref. letter frOll S. BLOOll CUSNRC) to T.L.

Patterson (OPPD) dated Decelllber 3, 1993.

Fluence based on data provided in a Deceamr 15, 1992 Letta frm S. L1Brun1 CPSEIG) to USNRC.