View source for L-77-326, Responding to Letter of 5/20/1977, Letter Transmitting Information Regarding Reactor Vessel Material Surveillance Program

{{Adams
| number = ML18227B789
| issue date = 10/21/1977
| title = Responding to Letter of 5/20/1977, Letter Transmitting Information Regarding Reactor Vessel Material Surveillance Program
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Lear G
| addressee affiliation = NRC/NRR
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person = 
| case reference number = L-77-326
| document type = Letter type:L, Technical Specifications
| page count = 18
}}

=Text=
{{#Wiki_filter:NRC FoRM 195.                                         U.S. NUCLEAR REGULATORY CO'SSION OOCKE (2 76I ww NRC  DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO:                                            FROM:                                   DATE OF DOCUMENT Florida  Power &   Light  Company                  10/21/77 Mr. GeDrge Lear                         Miami, Florida                          DATE RECEIVED Robert Eo Uhrig                                    10/26/77 ELETTER               0 NO TO R I 2 E 0        PROP                  INPUT FORM        NUMBER OF COPIES RECEIVED BG N C LASS I F I E D ABORIGINAL SCOPY                                                                                       3 sic   p~
DESCRIPTION                                                   ENCLOSURE g< o~<        5->-77 (fa "Turkey Point Unit Noi 3 Reactor Vessel Material Surveillance Program" "Florida Power & Light Company << Turkey Point Unit No~ 3 Reactor Vessel Radiation Surveillance Program" DISTRIBUTION FOR i~fATERIAL ON REACTOR VESSEL DATA PER R. INGRAM 5-26-77 PLANT NAIIE: . Turkey Point Units       3 & 4 RJL             10.26/77        (1>>P)       (12-P)+(/1-P)    ( Pg/I..      gQ./NCAA PePROb SAFETY                               FOR ACTION/INFORMATION BRANCH  CHIEF:
ZWETZIG INTERNAL D ISTR I BUTION MIPC PANLICKI EISENHUT BUTLER GRIMES HAZELTON HOGE R. GABLE RANDALL EXTERNAL DISTRIBUTION
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                                                        . BOX 013100, MIAMI, FL 33101 FLORIDA POWER & LIGHT COMPANY October 21, 1977 L-77-326 Office of Nuclear Reactor Regulation Attention: Mr. George Lear, Chief                Pt%
Operating Raactcra Branch $ 3 Division of Operating Reactors 8~i  @         4~       8 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

==Dear Mr. Lear:==

Re:   Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Reactor Vessel Material Information Your  letter of May 20, 1977 contained a Request for Information regarding the Reactor Vessel Material Surveillance Program at Turkey Point Units 3 and 4. On July 6, 1977 (L-77-2ll), we agreed to supply the information by October 22, 1977. The information you requested is attached.
Very  truly yours, obert E. Uhrig Vice President REU/MAS/cpc Attachment cc:   Mr. James P. O'Reilly,        Region II Robert Lowenstein, Esquire p-~(
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TURKEY POINT UNIT NO. 3 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluence (E,> 1 Mev) at the inneI      surface of the reactor vessel wall as of March 31, 1977 is 5.65 x      10'/cm     .
2.) The  effective full   power years  (EFPY) of operation accumulated   as of  March 31, 1977   is 2.87 EFPY.
3.) Fabrication of the reactor vessel     was performed by the Babcock and  Milcox  Company.
4.) a.)   A sketch of the reactor vessel showing all materials in the beltline region is shown in Figure l.
b.) Information on each of the welds in the beltline region is shown in Tables  1 through 4.
c.) Information    on each of the forgings    in the beltline region is shown  in Tables 4 through 7.
5.) Information relative to weld and forging material included in the material surveillance program is shown in'Tables 1 through 3 and 5 trough 7.

FIGURE 1 IDENTIFICATION AND LOCATION OF BELTLINE REGION MATERIAL IN THE TURKEY POINT UNIT NO. 3 REACTOR VESSEL ~
Cl       122S146VA1 M
N O
SA-1484
                                        '23P461VA1 Core SA-1101 123S266VAl

TABLE  1 IDENTIFICATION OF REACTOR VESSEL TURKEY POINT UNIT NO. 3 REACTOR VESSEL BELTLINE REGION WELD MATERIAL Weld Wire                Flux Wel d                 Weld          Wel d                                                            Post Weld Location              Process      Control No.      ~Te        Heat No.   ~T e        Lot No.        Heat Treatment Nozzle Shell to        Submerged Arc     SA-1484       Mn Mo Ni     72442   Linde 80       8579       1100-1125'F-48 Hrs-FC Inter. Shell Inter. Shell to        Submerged  Arc    SA-1101       Mn Mo Ni     71249   Linde 80       8445       1100-1125'F-48 Hrs-FC Lower Shell I
Surveillance  Weld    'Submerged Arc     SA-1101       Mn Mo Ni     71249   Linde 80       8445       1125'F-10 1/4.Hrs-FC TABLE 2 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION WELD MATERIAL Weld Wire                   Flux                               Wei  ht Percent We.l d Control No.    ~Te        Heat No.     ~Te        Lot No. C        P      S        Mn         Si      Mo      Ni     Cr  Cu SA-1484     Mn Mo  Ni    72442     Linde 80       8579    ,08     .018   .015     1.52       . 42.    .39     .66    .06 SA-1101     Mn Mo  Ni    71249     Linde 80       8445    .07     .021   .014     1.28       .52      .36     .57    .17 .21 Surveillance  Weld                                        .076    .011   .018     1.26       .66       42      57     14  31

CC TABLE 3  .
MECHANICAl PROPERTIES OF VESSEL BELTLIHE REGION WELD MATERIAL Weld Wire          . Flux                   Energy         Shel f Weld                                                    HDT*   at 10'F     NDT Energy   YS        UTS  Elong.
Control No.     ~Te        Heat No.     ~Te      Lot Ho;    'F     ft-1 b    oF   ft-lb   ksi        ksi SA-1484     Mn Mo  Ni     72442     Linde 80    8579     0      40,52,41    0                    84 00 SA-1101     Mn Mo  Hi     71249     Linde 80    8445      0     45,45,46 -
0          68. 63    84.26   28.5 Surveillance  Weld                                        0     26,37,25    3   64.5   76.30     92.35   24.9
  *Estimated Per  NRC   Standard Review Plan Section 5.3.2.
I TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT VESSEL INNER WALL LOCATIONS Fluence Shell For in or Weld Location                                            '/cm Nozzle Shell Forging                                                       ssxiO" Nozzle Shell to    Inter. Shell Circle  Seam                               9.5 x  10 Inter. Shell Forging                                                       6.3 x 10 Inter. Shell to    Lower Shell Circle  Seam                                6.3 x  10 Lower   Shell Forging                                                      6.3 x  10

TABLE 5 IDENTIFICATION'OF 'VESSEL'BELTLINE REGION 'SHELL FORGING MATERIAL Heat Treatment Material
  ~Com  onent     ~Fi       N. tl   tN.         ~5            ~So   lier    Austeni ti ze              ~Tem   er          Stress Relief Nozzle Shell      -122S146VA1     122S146       .A508 CL 2      Bethlehem    1550'F-ll   HR-Wg      1220'F-22    HR-AC     1125'F-40 HR-FC Inter. Shell      123P461VAl      123P461        A508 CL 2      Bethlehem    1550'F-13   HR-Wg      1210'F-18    HR-AC     1125'F-40  HR-FC Lower   Shell     123S266VAl      123S266        A508 CL 2    - Bethlehem    1550'.F-13 HR-Wg  -
1210'F-18    HR-AC .
1125'F-40  HR-FC Surveillance Material - Inter.       and Lower   Shell as Above Except Stress Relieved by Westinghouse                     1125'F-10 1/4   H TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL For  in  No.        C        Mn           P           S           Si                Mo         Cr         V          Co         Cu 122S146YA1         .22      .64        .010         .013         .25               .59        .35        .03        .014 123P461VA1         .20      .65        .010         .010         .26    .70        .62        .40        .02        .011       .058*
     -123S266VA1        .20      .62        .010         .008         .20    .67        .59      ..38        ;02         .016       .079*
     "Analyses Performed by Westinghouse as Part of Surveillance Program

TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Shel f*
TNDT    RTNPT      Energy      YS       UTS     Elong.       RA For  in  No.      oF       oF       ft-lb      ksi       ksi                  x 122S146VA1        50   . 50       98.5      64.0      85.5      26.0      69.95 123P461VA1        40       40       98.5      68.0      90.7      25.0      68.35 123S266VAl        30       30      117.5      58.1      83.4      28.0      71.40 123P461VA1   .             40       94.0      64.4      96.2      26.1      70.35 Surveillance 123S266VA1                 30       96.0      57.4      92.6      26.1      70.70      Test Data.
*Estimated From Test Data in the Major Working Direction Per    NRC Standard Review Plan Section 5.3.2

TURKEY POINT UNIT NO. 4 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.) The estimated maximum fluen:e (E > 1 Mev) of the jnner surface      of the reactor vessel as of March 31, 1977 is 4.79 x 101~ n/cm".
2.) The effective   full   power years (EFPY) of operation accumulated as of March 31, 1977 is 2.43 EFPY.
3.) Fabrication of the reactor vessel     was performed by the Babcock and Hilcox Co.
4.) a.)  A  sketch of the reactor vessel showing     all materials in the  beltline region is  shown in Figure 1.
b.) Information     on each  of the welds in the beltline region is   shown  in Tables   1 through 4.
c.) Information     on each  of the forgings in the beltline region is   shown in Tables   4  through 7.
5.) Information relative to weld and forging material included in the material surveillance program is shown in Tables 1 through 3 and 5 through 7.

FIGURE IDENTIFICATION AND LOCATION OF 1
t BELTLINE REGION MATERIAL IN'THE TURKEY POINT UNIT NO. 4    REACTOR VESSEL
                                                 ~ ~
124S309VA1 Wf 70 5   WF 67 123P481VA1 Core                         SA-1101 122S180VA1

TABLE   1 IDENTIFICATION OF REACTOR VESSEL TURKEY POINT UNIT N0.4 REACTOR VESSEL BELTLINE'REGION'WELD MATERIAL Meld Mire                   Flux Meld                  Weld          Meld                                                                     Post Weld Location                Process     Control No.          ~T  e        Heat No.    ~T   e       Lot No.       Heat Treatment Nozzle Shell to        Submerged Arc       NF  70-       Mn-Mo-Ni          72105    Linde 80         8669       1100-1150'F-48    HR Inter. Shell            Submerged Arc       WF-67        Mn-Mo-Hi          72442    Linde 80         8669       1100-1150'F-48    HR Inter Shell to          Submerged Arc       SA-1101      ttn-Ho-Hi         71249    Linde 80         8445       1100-1150'F-48    HR Lower Shell Surveillance Weld       Submerged   Arc     SA-1094      Mn-Mo-Ni          71249    Linde 80         8457       1125'F-10 1/4    HR-FC TABLE 2 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION WELD t@TERIAL Meld Mire                 Flux                                             Wei   ht Percent Meld Control No.     ~T  e      Heat Ho.       ~Te        Lot No.         C       Mn        P         S         Si        Ni     Mo       Cr  Cu MF-70       Mn-tIo-Ni      72105     Linde 80       8669        .070      1.60   .014       .011       .48       .46     .40     -   .27 MF-67       Mn-Mo-Ni       72442     Linde 80       8669        . 064     1. 49  . 014      . 01 7     . 54  ..  .57     .41      .02 SA-1101     Mn-Mo-Hi       71249      Linde 80      8445        .070    -
1.28   .021       ,014       .52       . 57    .36      .17 .21 SA-1094                    71249      Linde 80      8457        .070      1.42   .020       .016       .51        .55    .49      .16 .23 Surveillance Meld                                               .098      1.44    .014      .011       .50        .60    .36      .14 .30

d
'f

TABLE 3 MECHANICAL PROPERTIES'OF      VESSEL'ELTL'INE'REGION WELD'MATERIAL Weld Wire                   Flu x
* Energy  RT
                                                                                     '* Shel f Weld                                                         NDT     at 10'F    NDT   Energy   YS          UTS  Elong. RA Control No.   ~Te         Heat No.      ~Te        Lot No.       F     ft-lbs     'F    ft-lb   ksi          ksi    x     x WF-70      Mn-Mo-Ni      72105      Linde 80       8669      0     39,35,44     0            69.0         85.5   25. 8 64.7 WF-67      Mn-Mo-Ni      72442      Linde 80       8669      0     29,35,30     0            64.0         81.5   31.3  65.8 SA-1101    Mn-Mo-Ni      71249-  . Linde 80.      8445      0     45,45,46     0            68. 6        84. 3  28.5 SA-1094    Mn-Mo-Ni      71249      Linde 80       8457            38,34,52     0            72.5         86.0   26.7  65.1 Surveillance  Weld                                           0     29,39,36     0      66    70.2   '1.3         23.8  6C 7
  *Estimated Per  NRC  Standard Review Plan Section 5.3.2 TABLE 4 MAXIMUM END-OF-LIFE FLUENCE AT'VESSEL INNER WALL LOCATIONS Fluence Shell For in or- Weld Locations                                              n/cm Nozzle Shell Forging                                                          9.5 x   10 Nozzle Shell to    Inter. Shell Circle     Seam                               9.5 x   1.0 19 Inter. Shell Forging                                                          6.3 x 10 Inter. Shell to    Lower Shell Circle     Seam                                6.3 x 10 Lower Shell Forging                                                           6.3 x 10

e ~
TABLE 5
                                'IDENTIFICATION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Heat Treatment
  ~Ct Nozzle Shell
                 ~Fi      N 124S309VA1
                             . II   t 124S309 II Material
                                                  ~Sec.
A508 CL 2
                                                               ~Su Bethlehem lier          Austenitize 1550'F-15  HR-Wg
                                                                                                                     ~Tem   er 1220'F-22 HR-FC Stress Relief 1125'F-40 HR-FC Inter. Shell     -123P481VAl       123P481      A508 CL 2     Bethlehem                 1550'F-10 1/4HR-Wg      1210'F-18    HR-AC   1125'F-40    HR-FC Lower Shell      12S180VAl         122S180      A508 CL 2     Bethlehem                 1550'F-10 1/2  HR-Wg    1200'F-18    HR-FC    1125'F-40   HR-FC Surveillance Material - Inter.        and Lower  Shell as Above Except Stress Relieved by Westinghouse                               1125'F-10 1/2 HR-     C TABLE 6 CHEMICAL COMPOSITION OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Wei  ht Percent For in   No.                                                              Si         Ni        Mo        Cr                      Co        Cu 124S309VA1        .20         .60        .010        .012       .27                 .70       .57      .33          .02        .008 123P481VA1        .21         .65        .010        .011       .25                 .69       .59      .33         ..02        .011 122S180VA1        .22         .60        .010        .009       .23                 .74       .60      .34          .02        .013 123P481VAl*       .22         .67        .010        .009                           .71       .56      .33          .002       .017        .054
                                                                                      ..70
                                                                    .20'22S180VA1*
                      .21         .67        .011        .009       .23                           .56      .31          .001       .015        .056
    *Surveillance Material Analysis Performed         by Westinghouse.

TABLE 7 MECHANICAL PROPERTIES OF VESSEL BELTLINE REGION SHELL FORGING MATERIAL Shel  f*
Energy                         Elong.
For in   No.
NDT OF NDT oF      ft-1 b YS ksi UTS ksi        t         RA x
124S309VA1      40    '0          101       66.1       89.5       26.2      69. 3 123P481VA1       50      50        93       71.0       93.2       25.0      67. 2 122S180VA1      40       40         97      72.2       92.7       24.0      66.9 123P481VA1               50                 68. 5      90.1       25.4      68.1 Surveillance 122S180VA1               40                 70.8       91.5       24.2      67.8       Test Data 86
*Estimated From Test Data in the Major Working Direction Per  NRC  Standard Review Plan Section 5.3.2}}