ML20134D514

Forwards Proposed Revs to FSAR Re Fracture Toughness of RCPB Matls to Resolve SER Confirmatory Issue 17,per NRC Request.Changes Will Be Incorporated in Future FSAR Amend

ML20134D514
Person / Time
Site:	Perry
Issue date:	08/09/1985
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
PY-CEI-NRR-0313, PY-CEI-NRR-313, NUDOCS 8508190257
Download: ML20134D514 (11)

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- 2 P.O. box 5000 - CLEVELAND, OHlo 44101 - TELEPHONE (216) 622-9800 t - ILLUMINATING BLoG. - 55 PUBLICSQUARE Serving The Best Location m the Nation -

RRAY R. EDELMAN TflCE PRESIDENT i NUCLEAR l August 9, 1985 )

PY-CEI/NRR-0313 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Fracture Toughness RCPU Materials SER Confirmatory Issue 17

Dear Mr. Youngblood:

Attached are proposed revisions to the FSAR associated with fracture toughness of the Reactor Coolant Pressure Boundary (RCPB) materials as requeated by your stuff. These will be incorporated in a future FSAR amendment. A Technical Specification bases page associated with this revision is also attached.

We believe this information is sufficient to resolve SER Confirmatory Issue Number 17 in the next SER Supplement.

Very truly yours, Murray R. Edelman f~

Vice President Nuclear Group MRE:njc Attachment ec: Jay Silberg, Esq.

John Stefano (2)

J. Grobe 8508190257 05080'?

PDR ADOCK 05000440 E PDR Booi i ,t

5.3.2.1.2 Temperature Limits for Preoperational System Hydrostatic Tests and ISI Hydrostatic or Leak Pressure Tests

{

s f Based on 10 CFR 50 Appendix C, if there is no fuel in the reactor during system hydrostatic pressure tests or leak tests, the minimum permissible test temperature is 1000 F at 1563 psig for Perry Units 1 and 2.

The fracture toughness analysis for system pressure tests resulted in the curves labeled A shown in Figures 5.3-2 (Perry 1) and 5.3-3 (Perry 2). The curves labeled " core beltline" are based on an initial RTNDT of 10'F for the plate l material for Perry 1, and an initial RTNDT of -200F for the plate material for Perry 2.

The predicted shift in the RTNDT from Figure 5.3-5 (based on neutron fluence at 1/4 T of the vessel wall) must be added to the beltline curve to account for the effect of fast neutrons.

5.3.2.1.3 Operating Limits During Heatup, Cooldown and Core Operation The fracture toughness analysis was done for the normal heatup or cooldown rate of 1000F/ hour. The temperature gradients and thermal stress effects corresponding to this rate were included. The results of the analyses are a set of operating limits for non-nuclear heatup or cooldown shown as curves labeled B on Figures 5.3-2 and 3. Curves labeled C on Figures 5.3-2 and 5.3-3 apply whenever the core is critical.

5.3.2.1.4 Reactor Vessel Annealing In place annealing of the reactor vessel because of radiation embrittlement is unnecessary because the predicted value in transition of adjusted reference temperature does not exceed 2000F.

5.3-14

I TABLE 5.3-1 CHARPY TEST RESULTS AND CHEMICAL COMPOSITION A. PERRY UNIT I I. VESSEL BELTLINE MATERIAL IDENTIFICATION A. Number 2 Shell Ring Plates - Pc. 22-1-1, Heat C2557, Slab 1 Pc. 22-1-2, Heat B6270, Slab I Pc. 22-1-3, Heat A1155, Slab 1 B. Welds in No. 2 Shell Ring Vertical Seams Seam BD - Type E8018NM, Heat 627260, Lot B322A27AE Type E8018NM, Heat 626677, Lot C301A27AF Type RACO-1NMM, Heat SP6214B, Lot 0331 Seam BE - Type E8018NM, Heat 624063, Lot C228A27A Type E8018NM, Heat 626677, Lot C301A27AF Type E8018NM, Heat 627069, Lot C312A27A Type RACO-1NMM, Heat SP6214B, Lot 0331 Seam BF - Type E8018NM, Heat 627260, Lot B322A27AE Type E8018NM, Heat 626677, Lot C301A27AF Type RACO-1NMM, Heat SP6214B, Lot 0331 II. CHEMICAL ANALYSES FOR BELTLINE MATERIAL A. Plates C Mn P S Cu Si Ni Mo V Al Pc. 22-1-1, HL C2557 .23 1.32 .010 .025 .06 .27 .61 .54 .001 .039 Pc. 22-1-2, HL B6270 .20 1.28 .012 .015 .06 .23 .63 .53 0 .039 Pc. 22-1-3, Ht A1155 .20 1.33 .010 .013 .06 .28 .63 .54 .002 .031 B. Welds C Mn Ni Si Mo Cu P S V Ht. 627260 Lot B322A27AE .04 1.25 1.08 .56 .64 .06 .020 .022 .02 Ht. 626677 Lot C301A27AF .048 1.10 .85 .56 .45 .010 .015 .022 .009 Ht. SP6214B Lot 0331 .051 1.39 .82 .53 .52 .02 .013 .017 .004 Ht. 624063 Lot D228A27A .041 1.12 1.00 .41 .54 .03 .009 .018 .01 HL. 627069 Tot C312A27A .037 1.07 .94 .60 .52 .010 .013 .019 .012 l i (

l 5.3-27

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TABLE 5.3-2 UNIRRADIATED FRACTURE TOUGHNESS PROPERITES 9

A. PERRY UNIT 1 Plates Drop Wt. Transverse CVN Reference Upper Ht.No. NDT(*F) Ft-lbs MLE Temp. Temp.('F) Shelf (Ft-lb)

C2557-1 Top -20 52,50,52 42,46,42 +70F 10 84 Bottom. l

-20 54,64,76 63,53,46 +60F B6270-1 Top -40 53,78,56 43,58,44 +20F Bottom -30 63,63,64 51,51,52 +30F -30 94 A1155-1 Top -20 65,63,67 54,60,52 +50F -10 114 l Bottom -20 54,66,85 68,55,44 +40F Weld Drop Wt. CVN Reference Upper Metal NDT(*F) Ft-lbs MLE Temp. Temp.(*F) Shelf (Ft-lb)

Ht. 627260 -40 52,56,51 36,37,35 +30F -30 104 l Lot B322A27AE Ht. 626677 -40 53,51,54 36,37,35 +40 -20 90 Lot C301A27AF Ht. SP6214B -50 56,50,54 45,41,46 +10 -50 88 Lot 0331 -40 50,61,64 46,50,52 +10 -40 96 Ht. 624063 -60 57,59,68 37,38,46 +10 -50 105 Lot 228A27A Ht. 627069 -60 72,64,78 52,48,56 0 -60 112 Lot C312A27A l f

1 5.3-29 i

j 1

4 TABLE 5.3-2 (Continued)

B. PERRY UNIT 2 Plates Drop Wt. Transverse CVN Reference Upper Ht.No. NDT(*F) Ft-lbs NLE Temp. Temp.(*F) Shelf (Ft-lb C3474-1 Top -30 54 .54,53 44,44,44 +40F -20 95 Bottom -40 51',63,69 41,45,51 +20F C3560-1  !

Top -30 92,86,68 71,56,62 +30F Bottom -30 54,74,64 58,62,46 +40F -20 125 C3560-2 Top -30 70,52,61 44,54,49 +30F I Bottom -30 60,66,76 62,52,48 +40F -20 107 Weld Drop Wt. Transverse CVN Reference Upper Metal NDT(*F) Ft-lbs MLE Temp. Temp.(*F) Shelf (Ft-lb Ht. 422K8511 -80 65,74,127 44,48,76 -20F -80 143 Lot G313A27AD Ht. 492L4871 -90 50,51,57 36,38,40 0F -60 151 Lot A421B27AE Ht. 04T931 -90 65,69,72 52,48,50 0F -60 148 Lot A423B27AG Ht. SP6756 -60 55,66,63 54,51,57 0F -60 89 Lot 0342 (Single Wire)

Ht. SP6756 -50 64,79,77 35,72,55 +10F -50 95 Lot 0342 80,72 69,60 (Tandem Wire) l i

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l 5.3-30

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TA512 5.3-3 EOL BELTLIIE FIATE RTgyy & WELDS

, UNIT I A. Beltline Plates Reg. Cuide Asm NB-2300 1.99 Extrap. Eatinated meat WT ICu W ZF Start RTNDT ARTNDT (OF) EOL RTgDT (OF) i C2557.!(2) .06 .010 10 34 +44 (Limitins Plate) 36270-1 .06 .012 -30 40 +10 .

l All55-1 .06 .010 -20 34 +14 B. Beltline Welds i

Reg. Guide ASE NS-2300 1.99 Extrap. Estimated Weld Wire Flux y Weld Seam Beat /Imt WT ICu WT IF Start RTNOT ARTamT (OF) EOL RTNDT (OF) Type Type

! BD, SF 627260/5322A27AEI3) .06 .02 -30 67 +37 E8018MM --

} BD, BE, BF 626677/C301A27AF(3) .01 .015 -20 50 +30 E80180et --

l l

BE 624063/D228A27A .03 .009 -50 30 -20 E80181st --

BE 627069/C312Aj7A .01 .013 -60 43 -17 E8018MM -

BD, BE, BF SP6214B/03Yr(3) .02 .013 -40 43 +3 mA00 llem Linde 124 (Single Wire) l C. Test Plate Weld Material 2

Reg. Cuide ASE M5-2300 Estimated 1.99 Extrap.

Heat / Lot WT ICu UT IF Start RTNDT ARTN DT ( F) EOL RTNDT ( F) l 624039/D205A27A(3) .028 .015 -90 50 -40 1 07R458/S403827AC(3) .04 .02 -60 67 +7

40lF2871/H430827AF(3) .03 .013 -50 43 -7 i

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/

. TABLE 5.3-3 (Cont'd)

Unt? 2 A. Beltline Plates Rag. Cuide ASE 115-2300 1.99 Extrap. . Estimated Beat W ICu UT IF Start RTNDT ARTN DT (DF) EOL RTugyr (OF)

C3474-1(2) .09 .031 20 44 +24 (Limiting Plate)

C3560-1 .07 .010 -20 34 +14 C3560-2 .07 .010 -20 34 +14

3. Belttime Welde Reg. Cuide ASE NS-2300 1.99 Extrap. Estimated Weld Wire Flux

? Weld Sese Beat /Imt WT ICu WT IF Start RTEDT ARTET (OF) EOL RTMDT (DF) Type Type Y

50, BE, BF 422E8511/C313A27AD(2) .01 .016 -80 54 -26 E8018eet -

BD, BE, BF 492L4871/A421527AE(3). .04 018 -60 60 0 E8018tDI -

BD, BF 04T931/A423527AC(3) .03 .020 -60 67 +7 E80181st -

BD, BE, SF SF6756/0342(1)e(3) .08 .010 -60 34 -26 RACO 18998 Linde 124 (Single Wire)

BD, BE, BF SP6756/0342(Ile(3) 09 .010 -50 40 -10 RACO Imet Linde 124 l (Tanden Wire) l C. Test Plate Weld Material Reg. Cuide ASE NB-2300 1.99 Extrap. Estimated West / Lot WT ICu WT IF Start RTNDT ARTNDT ( F) EOL RTMDT (OF) 05T776/L314A27AR(3) .06 .015 -70 50 -20 All materials in (B.) were also used in the surveillance test plate fabrication.

NOTES:

1 Submerged ARC welding

2. Serveillance Test Plate 3 Surveillance Weld Material

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C.- Reactor Pressure, Perry Unit 2 Figure 5.3-3

FIGURE 5.3-4 IIAS BEEN DELE 7 FED

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REACTOR VESSEL TOUGHNESS E

HIGHEST I. BELTLINE ^ END 0 !fE HELF s COMPONENT MATERIAL HEATf/ LOT # CU(%) P(%)

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ENERGY (Ft-Lb) p NOT

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Plate SA533 GrB C2557-1 .06 - .010 +10 75 + 44 l.

Class 1 Weld BD,BF 627260/8322A2/AE .06 .020 -30 75 +37 l.

. II. NON-BELTLINE HIGHEST STARTING COMPONENT MATERIAL RTNOT( F)

• Shell Ring SA 533 Gr.B. C1.1 +10

" Botton Head ' SA 533 Gr.B. C1.1 +10 Top Head SA 533 Gr.B. C1.1 +10 Top Head Flange SA 508, C1.2 +10 ts 7.J Vessel Flange SA 508, C1.2 +10 Ov1 Feedwater Nozzle SA 508, C1.2 -20 go Veld Low alloy steel per  :*3 GE purchase specification -20 Q m

45 ft-lb & 25 mils lat. exp G Closure Studs SA 540 Gr.823 requirement met at +10(*F) @

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