View source for 0CAN109305, Responds to Generic Ltr 92-01 Re Rv Structural Integrity. Licensee Will Use Topical Repts BAW-2192P & BAW-2178P as Licensing Bases for Unit 1 to Demonstrate That All Beltline Welds Meet Fracture Toughness Requirements

{{Adams
| number = ML20059C334
| issue date = 10/29/1993
| title = Responds to Generic Ltr 92-01 Re Rv Structural Integrity. Licensee Will Use Topical Repts BAW-2192P & BAW-2178P as Licensing Bases for Unit 1 to Demonstrate That All Beltline Welds Meet Fracture Toughness Requirements
| author name = Yelverton J
| author affiliation = ENTERGY OPERATIONS, INC.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000313, 05000368
| license number = 
| contact person = 
| document report number = 0CAN109305, CAN109305, GL-92-01, GL-92-1, NUDOCS 9311010111
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 14
}}

=Text=
{{#Wiki_filter:.
  ~ . A                                                                                   t.,,ro ,o ,e,. i..... .
9 ENTERGY ll"%$)%
id 501&A 8888
                                                                                        - Jerry W. Yelverton he Prtahd 0;xnhons ANO October 29,1993 OCAN109305 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

==Subject:==
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Request For AdditionalInformation Regarding Generic Letter 92-01 " Reactor Vessel Structural Integrity" Gentlemen:
By {{letter dated|date=August 23, 1993|text=letter dated August 23,1993}} (0CNA089319), and received August 31,1993, the NRC requested that additional information be provided within 60 days of receipt to assist their review of Entergy Operations' response (0CAN079201) to Generic Letter 92-01 " Reactor Vessel StructuralIntegrity" for ANO Units 1 and 2.
Attachment 1 provides the responses to the request for additional information for~ ANO-1 and Attachment 2 provides the response for ANO-2.
Should you have any questions regarding this submittal, please contact me.
010025 9311010111 931029              C.                                                                      I    I PDR    ADOCK 05000313 P                     PDR      %w                                                                              ,

2     + - r        w  .u.s t e. s + .n   , s e+ -s       .x     .e a o 2 - e.- s -                            a , .' ,.                   s     qp,pa
         .i                                                                                                                                                   .
T':-
9 d
t 4
e  , ~ -*.
r a
e                                   =
                                                                                                                                                                        -6
                                                                                                                                                                     ..5 9
h m
9
                                                                                                                                                                        *L L
I J
t N
                                                                                                                                                                          +
5 C
P f
                                                                                                                                                                          -l i
I
                                                                                                                                                                            .I i
i l
                                                                                                                                                                       -1
                                                                                                                                                                       - i l
i l
l
                                                                                                                                                                       ,.. \
y -.,, y      Y-+       =- 5-- "-                  ,
e .
w--- ,_ -                   _ _ _ _ , __ , ,__ - - -                     -
                                                                                                                                              -am_.w__--*       --a

U..S.NRC October 29,1993 OC,AN109305 Page 2 Very truly yours, r
JWY/jrh Attachments To the best of my knowledge and belief, the statements contained in this submittal are true.
SUIf', SCRIBED AND SWORN TO before me, a Notary Public in and for MA<M /v County and the State of Arkansas, this //#Iday of .MM@                    ,
1993./
bxd: 1ilsnzo&rn           /
Notary Pu61ic My Commission Expires f/,/fa//, X/40 1

LU. S. NRC October 29,1993                                              ~'
OC,AN109305 Page 3                                             ,
cc:    Mr. James L. Milhoan Regional Administrator U. S. Nuclear Regulatory Commission Region IV
~
611 Ryan Plaza Drive, Suite 400
                      - Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801                               y Mr. Roby B. Bevan, Jr.
NRR Project Manager Region IV/ANO-1                   ,;
U. S. Nuclear Regulatory Commission                    '
NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike                                   ,
Rockville, MD 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory _ Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852

4 ATTACIIMENT 1 TO OCAN109305 Response to Request for AdditionalInformation (RAI)
ARKANSAS NUCLEAR ONE, UNIT 1 (TAC No. M83730)
Ouestion 2a in fiL 92-01 RAI #1 The response to GL 92-01 indicates that the initial upper-shelf energy (USE) value of 123 fl-lb for            ,
plate C5120-1 is from report BAW-1820. A review of report BAW-1820 reveals that the initial USE value of plate AYN 131 is unknown, and that all plate initial USE values listed there may be from longitudinal Charpy specimens. Further, Surveillance Report BAW-2075, Rev. I labeled all Charpy data in Table A-1 as " longitudinal", and Surveillance Report BAW-1440 reported that the initial longitudinal USE value is 132 f1-lb for the surveillance plate CSI14-1, close to the 129 ft-lb reported for the same plate in BAW-1820. Confirm orientation and update end-of-life (EOL) USE values for all plates. For plate AYN 131, either provide the Charpy USE or provide the Charpy USE and analysis from materials that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that this plate will meet the USE requirements of Appendix G,10 CFR Part 50. If this cannot be provided for plate AYN 131, or the updated EOL USE values for other plates are below 50 fl-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.
Response to RAI #1 This RAI is viewed as having two parts: (1) confirm orientation and update EOL USE values for all beltline plates; and (2) specifically address and justify a USE value for AYN 131. These two parts are addressed separately below.
(1) Table 1 presents the determination of end-of-life CyUSE for wrought beltline material at the
      % thickness location. It was indeterminate from mill documentation whether the Charpy specimens were taken in the transverse (weak) or longitudinal (strong) direction. Therefore, data for similar material from B&W 177-fuel assembly (FA) reactor vessel surveillance programs (RVSP) were assembled as shown in Table 2. It is evident by inspection of the values for CyUSE presented therein that the forging value shown in Table 1 is from the transverse (weak) direction and the plate values are from the longitudinal (strong) direction. The ratio of transverse-to-longitudinal Charpy values for this material is shown to be approximately 75%. However, in the Standard Review Plan (SRP), Section 5.3.2, a ratio of 65% is prescribed. Applying the SRP ratio to the lowest CvUSE in Table 1 (Heat No. C5120-1) results in a transverse predicted EOL CyUSE at 1/4T of 62 ft-lb, which exceeds the 10 CFR 50, Appendix G specified minimum of 50 fl-lb.
(2) The initial CyUSE of forging AYN 131 is not available; however, the initial CyUSE for similar forgings are available and are shown in Table 3; chemical compositions are shown in Table
: 4. The mean value ofinitial CyUSE for the forgings shown there is 124 fl-lb with a standard
                                                                                                                     )

k Attachment I to OCAN.109305 Page 2 of 7 deviation of 20. If the unusually low value for AWS 192 is deleted, the mean value is 130 n-lb        :
with a standard deviation of 14. The values are well in excess of the 75 R-lb minimum that is required by 10 CFR 50, Appendix G.
RAI#2                                                                                                 ;
The response indicates that the EOL USE value for weld WF-112 will fall below the screening criterion of 50 A-lb. An owners group report on USE equivalent margin analysis regarding beltline welds with low USE values for Levels A & B is under preparation by Babcock Wilcox Owners              l Group (B&WOG); a similar B&WOG report for levels C & D (BAW-2178P) is under NRC review now. The licensee must confirm that these two topical reports will be used as its licensing bases to demonstrate that all beltline welds will meet the USE requirements of Appendix G,10 CFR Part 50.
Response to RAI #2 Using the guidance in Regulatory Guide 1.99, Revision 2, the limiting beltline weld, WF-112, was reported to fall below a CyUSE value of 50 A-lbs before end-of-life. Accordingly, analyses in accordance with 10 CFR 50, Appendix G, Section V.C.3, were performed to demonstrate required margins of safety for continued operation. These analyses are reponed in BAW-2192P and BAW-2178P for load levels A & B and C & D respectively. These two topical reports will be         .
used as licensing bases for ANO Unit 1, to demonstrate that all beltline welds will meet the fracture toughness requirements of 10 CFR 50, Appendix G.
Question 2b in GL 92-01 RAI #3 The response provides the chemistry data for all beltline materials except weld SA-1788. Further      ,
investigation reveals that report BAW-1803 Revision 1 lists the copper and nickel contents of weld SA-1788 as 0.25% and 0.54%, while report BAW-2075. Revision 1 lists them as 0.29% and 0.47%. Resolve this discrepancy.                                                                      '
Response to RAI #3 For weld metal SA-1788, which is the lower shell-to-dutchman weld and is predicted to receive an end-of-life fluence of approximately 5.5 E 16 n/cm', the chemical composition values shown in surveillance report BAW-2075 Rev 1, Table A-1 (Cu=0.29, Ni=0.47) are obtained from the weld qualification report. The chemical composition shown in Table B-6 of BAW-1803 Revision 1, (Cu=0.25, Ni=0.54) is obtained from BAW-1500, Table 10. Both of these values are correct as referenced. The weld qualification value is based solely on the qualification analysis, while the BAW-1500 value is a statistical determination based on all analyses of filler wire heat 61782 welds. For licensing purposes, the B AW-1500. Table 10 value is preferred and so stated in section 2.3 of BAW-1820.

                   . - - . . . . . - - . - . .      . -- ~ . - .             -    -.              .-.
c-
       ~
         . Attachment I to OCAN109305 Page 3 of 7 RAI #4 The response indicates that a generic initial RTNDT of-5 F, which is the mean RTNDT value for -
34 Linde 80 welds (BAW-1803 Revision 1), has been used for all w,lds. Provide justification for not using the generic mean value for Linde 80 welds of 0 F as required by 10 CFR 50.61.             ,
Response to RAI #4 10 CFR 50.61(b)(2)(i), states that the initial RTNDT shall be 0 F for Linde 80 welds only if credible measured values are not available. BAW-1803 Revision 1, Tables 3-1 and 3-2 show -5 F to be the mean measured value of 34'Linde 80 welds and is presented as a credible measured value in accordance with the regulation.
l h
                                                                                                               ?
I l
l l
l l

4 Attachment I to OCAN109305                                                                                                                                     ,     _
Page 4 of 7 TABLE 1. PREDICTED END-OF-LIFE CyUSE FOR WROUGHT BELTLINE MATERIAL (1)                                          -
Material               Forging     Location           E-O-L              Copper            Predicted   Unirradiated    Predicted Heat                       or          in         % Thickness          Content            Drop (3)      CyUSE          E-O-L'                   -
Number                     Plate      Vessel       Fluence (2)           (wt %)               (%)         (ft-lb)     CyUSE(6)'
2 (n/cm )                                                             (ft-Ib)
* AYN 131        Forging              Lower Nozzle 5.2El8                   0.03              II(4)       124 (5)          110 Belt C5120-2        Plate                Upper Shell    5.9EIS                 0.17             23           133              102 C5114-2        Plate                Upper Shell    5.9E18                 0.15             21           133              105                       Li C5120-1        Plate                Lower Shell    5.6El8                 0.17             23           123              95                         !
C5114-1        Plate                Lower Shell    5.6El8                 0.15             21           129              102                         ,
NOTES:                                                                                                                                             .
(1)     

==Reference:==
BAW-1820, except where otherwise noted (2)     

==Reference:==
BAW-2108, Revision 1 (3)     Regulatory Guide 1.99, Revision 2, Figure 2 (4)     Beyond validity of Figure 2, extrapolated value (5)     Estimated value, see Response to RAI #1,- Part (2)
(6)     Unirradiated CyUSE reduced by predicted drop for end-of-life t
1

Attachment I to OCAN109305                                                                                                         ,
Page 5 of 7                                                                                                  -
                                                             ' TABLE 2. UNIRRADI ATED CyUSE 

==SUMMARY==
NSSS    PLATE OR          HEAT             CyUSE       CyUSE             RATIO   REFERENCE-FORGING          NUMBER     LONGITUDINAL TRANSVERSE            TRANS (ft-lb)      (fl-Ib)             TO LONG ANO-1                  Plate            C5114-1        132           96             73 %        BAW-2075,R1 Oconee-1               Plate            C3265-1        141           108            77 %        BAW-2050
* Crystal River-3        Plate            C4344-1       124            94             76 %        BAW-1898 TMI-l                  Plate            C2789-2       131            98             75 %        BAW-1901 Rancho Seco            Plate            C5062-1      -
90             -
BAW-2074 Oconee-2               Forging          AAW 163       152            133            88%         BAW-2051 Oconee-3               Forging          ANK 191       180            144            80 %        BAW-2128,R1 BAW-1438 -
AWS 192       160            112            70 %        BAW-1438 Davis Besse            Forging          BCC 241      -
127            -
BAW-1882,R1 AKJ 233      -
140 i

4                   1 Attachment I to -
OCAN109305                                                                                                                                    ,
Page 6 of 7                                                                                                                   -
TABLE 3. REACTOR VESSEL FORGINGS- (1)                                                                                           >
Forging              Forging           ' NSS Where                    Forging         Unirrad Number             Manufacturer                   Forging          Specification     CyUSE Located               (2)              (R-Ib)
AYN 131            Ladish                ANO-1                 A 508, Class 2 Code        -
Case 1332-2 ADB 203            Ladish                Davis-Besse           A 508, Class 2 Code      132 Case 1332-4 AKJ 233            Ladish                Davis-Besse           A 508, Class 2 Code      144 Case 1332-4 BCC 24i            Ladish                Davis-Besse           A 508, Class 2 Code      118 Case 1332-4 ANK 191            Ladish                Oconee-3              A 508, Class 2 Code      110 Case 1332-4 AWS 192            Ladish                Oconee-3              A 508, Class 2             90 Code Case 1332-4 AWG 164            Ladish                Oconee-2              A 508, Class 2           145 Code Case 1332-4 AAW 163            Ladish                Oconee-2              A 508, Class 2           128 Code Case 1332-4 i  NOTES:
(1) - 

==Reference:==
BAW-1820 (2) Code Cases 1332-2 and 1332-4 allow the use of A 508, Class 2 for Class A nuclear                                                                  i vessels in accordance with Section III.
w ,   -+r-- w   e   -m e    -,              ,-,,,ene.      w   - , w w n-      <-1   w s;~-r     s  , e , s -
er - _ cew. m  ,-- ,-     _ _ - . _ . .

Attachment I to OCAN109305                                                                                                            .
Page 7 of 7                                                                                               -
Table 4. CHEMICAL COMPOSITION OF REACTOR VESSEL- FORGINGS (1,2)
Forging            C      Mn       P      S             Si      Ni   Cr             Mo     Cu Number AYN 131                0.27   0.64     0.009   0 015         0.21    0.70 0.32           0.66   0.03 ADB 203                0.23   0.70     0.007   0.009         0.29    0.68 0.39           0.63   0.04 AKJ 233                0.26   0.68     0.004   0.006         0.30    0.77 0.38           0.64   0.04 BCC 241                0.22   0.63     0.011   0.011         0.27    0.81 0.32           0.63   0.02 ANK 191                0.24   0.72     0.014   0.012         0.21    0.76 0.34           0.62   0.02 AWS 192                0.21   0.58    0.011    0.015         0.24    0.73 0.30           0.60   0.01 AWG 164 -              0.21   0.62    0.010    0.010         0.23    0.80 0.39           0.58   0.02 AAW 163                0.24   0.63    0.006    0.012         0.25    0.75 0.36           0.62-  0.04 NOTES:
(1) 

==Reference:==
BAW-IS20 (2) Composition in weight percent

ATTACIIMENT 2 to DCAN109305 Response to Request for AdditionalInformation (RA1)
ARKANSAS NUCLEAR ONE, UNIT 2 (TAC NO. M83430)
Quntion 2b in GL 92-01 RAI #1 The response indicates that the initial RT,, values for plate C8009-1, -2, C8010-1, -2, -3, and weld 9-203 are -26, 0,12, -28, -30, and -10 F. The corresponding values in the pressurized thermal shock submittal dated January 22,1986, are 2 to 31 degrees higher.
The discrepancies were explained in a {{letter dated|date=May 8, 1991|text=letter dated May 8,1991}}, from ABB Combustion Engineering to Entergy Operations that, "The newer values (Reference 1) resulted from a more rigorous application of MTEB 5-2 to the data and the use of baseline surveillance data for the surveillance program plate (TR-MCD-002, March 1976)." Provide details about this new evaluation and its application to plates C8009-1,-2, and C8010 3.
Response to RAI #1

===Background===
Reference 1 specifies that the reactor vessel for ANO-2 was designed in accordance with Section III of the 1968 Edition of the ASME Boiler and Pressure Ve'ssel Code through the Summer,1970 Addenda. Since then, the fracture toughness requirements specified by Section III of the ASME Code have changed significantly. The values for initial RT,,
were therefore developed in accordance with Reference 2 to ensure that proper conservatisms were maintained.
Initial RT,, values are developed using results from both drop weight testing and Charpy impact tests (also referred to as Cy tests). Drop weight tests establish a temperature T,,
that is at or above the nil-ductility transition temperature of a material. Charpy impact test results are used to determine a temperature, Tcy, at which the material exhibits at least 50 ft-lb of absorbed energy and 35 mils lateral expansion. Paragraph NB-2331(a) of                ,
Reference 2 provides a step-by-step process which is used to determine T, Tcy, and initial RT,m.
This process is as follows:
: 1) Determine a temperature T,, that is at or above the nil-ductility transition temperature by drop weight tests.
: 2) At a temperature not greater than T,,+ 60 F, each specimen of the Cy test (NB-2321.2) shall exhibit at least 35 mils lateral expansion and not less than 50 fl-Ib absorbed energy. Retesting in accordance with NB-2350 is permitted. When these requirements are met, T,,is the reference temperature RT,m.

4
      ~
Attachment 2 to
          '0CAN109305                                                                                                  l
        . Page 2 of 4
: 3) In the event that the requirements of step 2 on the previous page are not met, conduct additional Cy t'sts  e     in groups of three specimens (NB-2321.2) to
* determine the temperature cy    T at'which they are met. -In this case the reference temperature RTym =T cy - 60 F. Thusl the reference temperature RT ym is the.
higher of T,m and (T   cy - 60'F).
: 4) When a Cy test has not been performed at Tym + 60 F, or when the Cy test at T,m + 60 F does not exhibit a minimum of 50 R-lb and 35 mils lateral expansion, a temperature representing a minimum of 50 n-lb and 35 mils lateral expansion may be obtained from a full Cy impact curve developed from the minimum data points -
of all the Cy tests performed.
Paragraph NB-2322.2 of Reference 2 specifies the orientation of Charpy impact test                        ;
specimens. For plate materials the specimen shall be oriented in a direction normal to the                 t principal rolling direction (transverse orientation) other than the thickness direction. The Charpy impact test specimens for ANO-2 reactor vessel plates were in a longitudinal                       !
orientation, parallel to the principal rolling direction. It was necessary to convert the                  :
longitudinal data to a transverse orientation to remain consistent with the guidelines for determining RT,, provided by Reference 2.
Branch Technical Position MTEB 5 2 provides guidelines to convert longitudinal Charpy                      ,
impact test results to a conservative estimate of the results that would have been obtained                !
for specimens with a transverse orientation (Reference' 3). Reference 3, Paragraph                        l B.1.l(3)(b) specifies that if longitudinally-oriented specimens were tested, then the                      '
temperature at which the specimens met the criteria of 50 n-lbs and 35 mils lateral expansion (Tcy) must be increased by 20 F. The values of T       cy that were extracted from the certified material test reports (CMTRs) for each of the reactor vessel plates were converted using this method.                                                                             .i Basic Data                                                                                                  !
The following information was exum-ted from CMTR.s for plates C-8009-1, C-8009-2, and C-8010-3 in order to determine the initial RT,, for the three plates:
Plate ID                Tum(F)                Longitudinal Tcy( F)
C8009-1                 -30                   14*
C8009-2                 0                    -24*                                        ;
C8010-3                 - 30                  10 i
l
                                                    -                             -        -     ~   .   -___-_____-_:

3
              '*                                                                                                                                           .f Attachment 2 to                                                                                                                     '1 I
OCAN109305 Page 3 of4                                                                                                                                !
* The value for T cy      was obtained in accordance with step 4 on the previous page.
A full Charpy impact curve was developed based on the minimum Charpy test data points, and the temperature corresponding to at least 50 fl-lb and 35 mils lateral                                             ,
expansion was obtained from tins cune.
Development ofinitial RT, Values The guidelines of Branch Technical Position MTEB 5-2 were used to convert the Charpy                                                      ;
test results (Tcyvalues for the plates) to a transverse orientation:
Plate ID                      Tcylongitudinal ( F)          T c, transverse ( F)
C8009-1                       14                            34                                                              .
C8009-2                       24                            44                                                                    !
                                                                                                                                                         .I C8010-3                       10                            30                                                                    l From NB-2331(a) (3) of Reference 2, the reference temperature RTyn is the higher ~of Ty, and (Tcy- 60 F):                                                                                                                      '
i Plate 1D                       Ty, (*F)                 Tcy- 60 ( F)           Initial RTy ,( F)
C8009-1                        -30                      -26                    -26                                                         i l
C8009                      0                        -16                    0                                                          ;
C8010-3                        -30                      -30                    -30 lksills Material information from the plate's CMTRs was used aiong with Branch Technical Position MTED 5-2 to develop conservative values ofinitial RTy , in accordance with current ASME Code guidelines. The initial RTy, for plates C8009-1, -2, and C8010-3 were determined to be'-26 F, O F, and -30 F, respectively.
1 1
l l

   .             -          = = .         -                --
       ,   Attachment 2 to r                                                                                                         :
OC.AN109305
         . Page 4 of 4 -
RAI #2                                                                                         !
The response reports two initial RT, values for weld 9-203: one is -40 F with the              ;
identification "9-203", and the other is -10 F with the identification "Sury.-Weld (Same      1 consumables as 9-203)"- Confirm that the initial RT, value of-10 F will be used in any future RT, calculation for weld 9-203 consistent with the justification given in the same letter mentioned above (dated May 8,1991).                                                     ;
Response to RAI #2                                                                             ,
t The RT, value of-10 F for weld 9-203 was utilized in the calculation of ANO-2's 21 EFPY Pressure-Temperature limits and the Pressurized Thermal Shock assessment (Reference 4). Entergy Operations intends to utilize this value in future evaluations unless   ,
more appropriate methods to calculate the initial RT, become available. Note that the          '
RT, value was changed to -10 F because it was believed that the new calculation was more appropriate and defendable.
References                                                                                     ;
l) NUREG-0308, Safety Evaluation Report, Oflice ofNuclear Reactor Regulation, U. S.           ;
Nuclear Regulatory Commission In the Matter of Arkansas Power and Light Company, Arkansas Nuclear One - Unit 2, Docket No. 50-368, dated November 11, 1977.
: 2) ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB,1989 Edition, No Addenda.
: 3) NRC Standard Review Plan 5.3.2, Revision 1, dated July,1981.
: 4) J. W. Yelverton to the U. S. Nuclear Regulatory Commission, " Proposed Change to the Technical Specification Pressure / Temperature Limits," 2CAN069109, June 18, 1991.                                                                                     ,
i l
j
                                       -                                                                  -}}