ML20198J564

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Unit 2 Pressure & Temp Limits Rept
ML20198J564
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 01/07/1998
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20198J090 List:
References
NUDOCS 9801140162
Download: ML20198J564 (44)
v • d • e


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BRAI3 WOOD. UNIT 2  !

r PRESSURE AND TEMPERATURE LIMITS REPORT - .

t TaWe of Contents  !

Section Page j

1.0 Introduction 1 2.0 Operating Limits 1 ,

2.1 RCS Pressure and Temperature (Pfr) Limits -1 l 2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints 2 f 2 i 2.3 LTOP Enable Temperature 2A Reactor Vessel Boltup Temperature 3 2.5 Reactor Vessel Minimum Pressurization Temperature 3 3.0 Reactor Vessel Material Surveillance Program 9 l

.4.0 Supplemental Data Tables i1 -

5.0 - References 18 i

Attachment  ;

WCAP-14824," Byron Unit 1 Ileatup and Cooldown Limit Curves for Normal Operation and t Surveillance Weld Metal Integration for Ilyron and 13raidwood," Revision 2, November 1997.

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BRAIDWOOD UNIT 2 l PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures :  !

n i Figure _ Page 1.1 - liraidwood Unit 2 Reactor Coolant System lleatup Limitations (lleatup Rates up to 4 100 'F/hr) Applicable for the First 12 EFPY (Without Margins for Instrumentation Errors) ,

2.2 liraldwood Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up 5 to 100 'F/hr) Applicable for the First 12 EFPY (Without Margins for Instrumentation Errors) 2.3 liraidwood Unit 2 Maximum Allowable Nominal PORV Setpoints for the Low 7 Temperature Overpressure Protection (LTOP) System Applicable for the '

First 12 EFPY

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BRAIDWOOD . UNIT 2 PRESSURE AND TEMPERATURE LIMITS REN)RT  ;

List of TsMes Table Page 2.1 13raidwood Unit 2 lleatup and Cooldown Data Points at 12 EFPY 6- [

(Without Margins for instrumenti. tion Errors) i 2.2 Data Points for 13raidwood Unit 2 Maximum Allowable PORY Setpoints 8 for the LTOP System Applicable for the First 12 EFPY 3.1 liraidwood Unit 2 Capsule Withdrawal Schedule 10-1

~41

.. 13raldwood Unit 2 Calculation of Chemistry Factors Using Surveillance 12 Capsule Data 4.2 Ilraidwood Unit 2 Reactor Vessel Material Properties 13 I

4.3 Summary ofliraidwood Unit 2 Adjusted Reference Temperatures (ARTS) at 14 the 1/4T and 3/4T Locations for 12 EFPY 4.4 Ilraidwood Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 15  :

12 EFPY at tlic Limiting Reactor Vessel Material Weld Metal WF562 (llased on i Surveillance Capsule Data) 4.5 RTns Valuer for llraidwood Unit 2 for 32 EFPY 16 4.6 . RTns Valurs for Israidwood Unit 2 for 48 EFPY 17 1

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HRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT i 1.0 Introduction s t

Reference to Technical Specifications (TS) numbers are given in both the tiraidwood Station t current Technical Specifications (CTS) and improved Technical Specifications (ITS). The CTS  !

number is presented first, followed by the ITS number in brackets [ ). <

This PTLR for Unit I has been prepared in accordance with the requirements of TS 6.9.1.ll/[lTS4 6]. Revisions to the PTLR shall be provided to the NRC after issuance.

The Technical Specifications addressed in this report are listed below:

1.CO 3.4.9.1 Pressure / Temperature Limits; and f LCO 3.4.9.3 Overpressure Protection Systems, i llTS LCO 3.4.3 RCS Pressure and Temperature (P/I)1.imits; and LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) Systern].  ;

I 2.0 Operating Limits The PTLR limits were developed using a methodology specified in the Technical Specifications.  !

The methodology listed in WCAP 14040 NP A (Reference 1) was used with four exceptions:

[

a. Use ofIINDF/Il IV neutron transport cross section library and IINDF/13 V dosimeter reaction cross sections,
b. Optional use of ASMi! Code Section XI, Appendix 0, Article 0 2000,1996 Addenda,
c. Use of ASMli Code Case N 514, and
d. Use of Rl! LAP computer code for calculation of LTOP setpoints for Unit I replacement steam  !

generators.

1

- WCAP 14824, Revision 2, is included as an attachment for reference. WCAP-14824, Rev. 2 contains the P/f curves for Ilyron Unit 1, along with the weld metal data integration for Ilyron and llraidwood Units 1 and 2 and the llyron/11raidwood fluence methodology justification for IINDF/ll VI cross sections.

2.1 RCS Pressure and Tempen., ore (P/r) Limits (LCO 3.4.9.1/ [lTS LCO 3.4.3]) ,

2.1.1 The RCS temperature rate-of changt limits defined in Reference 7 are:

a. A maximum heatup of 100'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period,
b. A maximum cooldown of 100'F in any 1-hour period, and
c. A maximum temperature change ofless than or equal to 10*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

1

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BRAIDWOOlb UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Operating Lismits (Continued) 2.1.2 The RCS P/r limits for heatup, inservice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.1. The RCS P/r limits for cooldown are shown in Figure 2.2 and Table 2.1. These limits are defined in Reference 7. Consistent with the methodology decribed in Reference 1, the RCS P/r limits for heatup and cooldown shown in Figures 2.1 and 2.2 are pmvided without margins for instrument error. The criticality limit curve specifies pressure temperature limits for core operation to provide additional margin during actual power production as specified in 10 CFR 50, Appendix 0.

The Pfr limits for core operation (except for low power physics testing) are that the reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydmstatic test, and at least 40*F higher than the minimum permissible temperature in the corresponding P/F curve for heatup and cooldown 2.2 1.ow Temperature Overpressure Protection (LTOP) System Setpoints (LCO 3.4.9.3/

[lTS.LCO 3.4.12]).

The power operated relief valves (PORVs) shall cach have maximum lifl settings in accordance with Figure 2.3 and Table 2.2. These limits are based on References 5,13 and

14. The Residual lleat Removal (Rii) Suction Relief Valves are also analyzed to individually provide low temperature overpressure protection. This analysis for the Ril Suction Relief Valves remains valid with the current Appendix 0 limits contained in this PTLR document and will be reevaluated in the future as the Appendix 0 limits are revised.

The LTOP setpoints are based on P/r limits which were established by 10 CFR 50, Appendix 0 without allowance for instrumentation error in accordance with the methodology described in Reference 1. The LTOP PORV maximum lift settings shown in Figure 2.3 and Table 2.3 account for appropriate instrument error.

2.3 LTOP Enabb Temperature The as analyzed LTOP enable temperature is 200*F (Reference 15).

The TS required enable temperature for the PORVs shall be 2 350'F RCS temperature.

(Braidwood Unit 2 procedures goveming the heatup and cooldown of the RCS require the arming of the LTOP System for RCS temperature of 350*F and below and disarming of LTOP for RCS temperature above 350*F).

Note that the last LTOP PORV segment in Table 2.2 extends to 450'F where the pressure setpoint is 2350 psig. This is intended to prohibit PORV lill for an iri dvertent LTOP system arming at power.

2 L

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BRAIDWOOD . UNIT 2 1

PRESSURE AND TEMPERATURE LIMITS REPORT Operating Lismits (Continued)  !

2.4 Reactor Vessel Bohup Temperature (Non Technical Specification)

[

'lhe minimum boltup temperature for the Reactor Vessel Flange shall be 2 60'F. Holtup is a condition in which the Reactor Vessel head is installed with tension applied to any swd, and ,

with the RCS vented to atmosphere (Reference 7).  ;

2.5 Reactor Vessel Minimum Pressurization Temperature (Non Technic:.1 Specification) i The minimum temperature at which the Reactor Vessel may be pressurized (i.e., in an unvented condition) shall be 2 60*F plus an allowance for the uncertainty of the  !

temperatu.e instrument, determined using a technique consistent with ISA S67.041994.-  !

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. _ . . _ - - . _ UNIT _ _ _ 2_ _ _ _ _ _ . _ _ . . _ . . . _ . _ _ _ . _

PRESSURE AND TEMPERATURE LIMITS REPORT 4

Material Proomy Buit LIMITING MATERIAL: CIRCUMFRENTIAL WELD (usas sun. capsule data)

LIMITING ART VALUES AT 12 ETPY: t/4T. 66.t'F 3/4T,38.I'F 2500 -

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Figure 2.1 Braidwood Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 100 'F/hr) ,

Applicable for the First 12 EFPY (Without Margins for Instrumentation Errors; Using 1996 Appendix G Methodolgy) a J

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BRAIDWOOD . UNIT 2 .

PRESSURE AND TEMPERATURE LIMITS REPORT Material Proneny Basis LIMITING MATEPJAL. CIRCUh0 reb 71AL %T.LD (unas sun. capsule data)

LIMITING ART VALUES AT 12 EFPY: t /4T. 66.9'F 3/4T. $8.I'T 2500 .

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Figure 2.2 Braidwood Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100'F/hr)

Applicable for the First 12 EFPY (Without Margins for Instrumentation Errors; Using 1996 Appendix G methodolgy) 9 1

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BRAIDWOOD . UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT  !

Tahle 2.1 BRAIDWOOD Unit 2 Hestup* and Cooldown* Data Points at 12 EFPY" (Using 1996 Appendix G Methodolgy Without margins for instrumentation errors)

HEATUP CURVES COOLDOWN CURVES 100 F Hootup Leak Test Curve Crit 6ceiny Limit Umst si edy stese 28 DEO F H DEO F 100 DEO F T i P T i P T I P T i P T I P T 1 P T I P

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    • For each cooldown rate, the steady state pressure values shall govern the temperature where no allowable pressure values are provided.

l 6

BRAIDWOOD . UNIT 2 .

PRESSURE AND TEMPERATURE LIMITS REPORT ,

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, ' i l il iii i ' i i I l l 1 i I I I il i i i i i i I l e 60 100 160 See 360 No see AUCTIONEERED LOW RCS TEMPERATURE (DEG. F)

Figure 2.3 Braidwood Unit 2 Maximum Allowable Nominal PORV Setpoints for the Low Temperature Overpressure Protection (LTOP) System Applicable for the First 12 EFPY 7

. -.w - - . - - -

BRAIDWOOD UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.2 Data Points for Braidwood Unit 2 Maximum Allowable PORV Setpoints for the LTOP System Applicable for the First 12 EFPY PCV 455A PCV-456 (2TY-0413M) (2TY 0413P)

WTIONEERED LOW RCS PRESSURE AUCTIONEERED LOW RCS PRESSURE RCS TEMP. (DEG. F) (PSIG) RCS TEMP. (DEG. F) (PSIG) 50 497 50 513 70 497 70 513 100 497 100 513 120 452 120 469 170 451 170 468 200 614 200 630 250 599 250 615 300 684 300 600 350 584 350 600 450 2350 450 2350 Note: To detennine maximum allowable lift setpoints for RCS Pressure and RCS Temperatures greater than 350'F, linearly interpolate between the 350'F and 450'F data points shown above.

8

HRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Reactor Vessel Material Surveillance Program The reactor vessel materist irradiation surveillance specimens shall be removed and analyzed to determine changes in material properties. The removal schedule is provided in Table 3.1. The -

results of these analyses shall be used to update Figures 2,1 and 2.2 and Table 2.1. The time of ,

, specimen withdrawal may be modified to coincide with those refueling outages or reactor shutdowns most closely approaching the withdrawal schedule.

The pressure vessel material surveillance program (Reference 6) is in compliance with Appendix il to 10 CFR 50," Reactor Vessel Radiation Surveillance Program." The material test

.equirements and the acceptance standards utilize the reference nil-ductility temperature, RTNtrr ,

which is determined in accordance with ASME Section III Paragraph NB 2331. The empirical 4

relationship between RTNtvr and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix G. " Protection Against Non Ductile Failure," to Section XI of the .

ASME Boiler and Pressure Vessel Code. The surveillance capsule removal schedule meets the requirements of ASTM E185-82.

e 9

t BRAIDWOOD - UNIT 2. _.

>r

=: _. ~

PRESSURE AND TEMPERATURE LIMITS REPORT ,

Table 3.1_ j t

Bmidwood Unit 2 Capsule Withdrawal Schedule  ;

Capsule -- Vessel Location Capsule Lead. Removal Time"' Estimated Capsule (Degrees) Factor (EFPY) Fluence (n/cm*) - l U- 58.5' ' - 4.00 - 1.13 (Removed) 3.933 x 10" a

X .238.5' 4.02 4.215 (Removed) j26 x 10"- j W- 121.5* 4.02 7.97 (EOL Wall) 2.199 x 10"N i 11.95 (1.5 EOL Z 301.5* 4.02 Wall M )- 3.299 x 10" V 61.0* 3.70 Standby ---

Y- 241.0" 3.70 Standby ---

(a) EfTective Full Power Years (EFPY) from plant startup. ,

(b) Maximum end of license (32 EFPY) inner vessel wall fluence.

- (c) Derived from Table C-4 of WCAP-14824, Rev. 2 (Reference 2, which is the Attachment to this report).

h p

s' 10

BRAIDWOOD. UNIT 2

~ PRESSURE AND TEMPERATURE LIMITS REPGRT i

- 4.0 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values -

shown were used as inputs to the Pff limits.

Table 4.1 shows the calculation of the surveillance material chemistry factors using surve.i llance capsule data.

Table 4.2 provides the reactor vessel material properties.

Table 4.3 provides a summary of the Braidwood Unit 2 adjusted reference temperatures (ARTS) at the 1/4T and 3/4T locations for 12 EFPY, Table 4.4 shows the calculation of ARTS at 12 EFPY for the limiting Braidwood Unit 2 reactor vessel material -Weld Metal WF562 (Based on Surveillance Capsule Data).

Table 4.5 provides the RTrrs values for Braidwood Unit 2 for 32 EFPY.

Table 4.6 provides the RTrrsvalues for Braidwood Unit 2 for 48 EFPY.

11

CRAIDWOOD - UN!T 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.1 Braidwood Unit 2 Calculation of Chemistry Factors Using Surveillance Capsule Data Fluence Material Capsule (n/cm2 , pp<o Measured FF*ARTsor (FF)2 E> l .0 ARTsor Mev), f Lower Shell Forging U 3.933 x10'8 0.741 0 0.000 0.550 50D102/30C97 -

(Tangential)

X 1.126 x10 l.033 3 3.099 1.067 Lower Shell Forging U 3.933 x10 O.741 5 3.707 0.550 50D102/50C97 (Axial) X 1.126x 10 l.033 35 36.160 1.067 Sum: 42.996 3.234 Chemistry Factor (* = 42.996 + 3.234 = 13.3*F Braidwood I Weld U 3.814x10 O.733 10(6 7.333 0.538 Metal WF562N X 1.144x10 l.038 25(4 25.95 1.077 Braidwood 2 i

Weld U 3.933x10 s 0.741 0 0 -0.550 Metal WF562(4 X l.126 x10 l.033 20(0 ,

20.66 1.067 Sum: 53.943 3.232

[ Chemistry Factor (* = 53.043+ 3.232= 16.7 F (a) FF = Fluence Factor = fm2:4:*ios n (b) Braidwood Unit 1- ARTunt values were obtained from WCAP-14243. (Reference 12).~

(c) Braidwood Unit 2 capsule fluence, FF, and ARTNnT values were obtained from WCAP-14970 (Reference 7).

(d) Cbemistry Factor = E (FF* ARTNur) / Z ((FF) 2),

- (e) ARTwor per Ratio Procedure of 10 CFR 50.61 (Reference 10) is not affected, since Ratio = 1.0.

See Table B.4 of WCAP 14824, Rev. 2 (Reference 2).

12 I

, , + - n -

BRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

. Table 4.2 Braidwood Unit 2 Reactor Vessel Material Properties Chemistry initial Material Cu (%) Ni (%)(*) Factor (') RT nar ('F)*)

Description -

Closure Head Not 0,75 -- 20(*)

Flange - Reported Vessel Flange 0.07 0.70 -- 20(')

Lower Shell 0.06 0.77 37.0 -30 '

Forging Upper Shell 0.03 0.71 20.0 -30 Forging Weld Metal 0.03 0.67 41.0 40 WF562 (a) Chemistry Factors are calculated from Cu and Ni values per Regulatory Guide 1.99, Position 1 (Reference 11).

(b) Initial RT orvalues N are measured, WCAP-14970 (Reference 7).

(c) Closure head and vessel flange Initial RTworvalues are used for considering flange requirements for the heatup/cooldown curves, WCAP-14970.

13

l u

HRAIDWOOD o UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT i

l Table 4.3 I

Summary of Braidwood Unit 2 Adjusted Reference Temperatures (ARTS) l at the 1/4T and 3/4T Locations for 12 EFPY L 12 EFPY Material Description 1/4T ART ('F) 3/4T ART ('F)

Lower Shell Forging 29.5 10.1 Using sun'elllance capsule data (RG Position 2(')) -8.6 -15.6 2.2 -8.3 Upper Shell Forg'ing '

(RG Position 1 ))

Weld Metal 105.9 84.4 (RG Position 1('))

Using credible 66.9*) 58.l*)

surveillance capsule dato (RG Position 2 I'))

(a) Calculated using a chemistry factor based on Regulatory Guide (RG) 1.99, Position I and Position 2. Note: Surveillance data for the lower shell forging was determined to be NOT credible per WCAP-14824 Rev.-2, however, the results are reported here for completeness. (Reference 11).

(b) These ART values were used to generate the Braidwood Unit 2 heatup and cooldown curves, WCAP-14970 (Reference 7).

14

ERAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

. Table 4.4 ,

Braidwood Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 12 EFPY at the Limiting Reactor Vessel Material Weld Metal WF562 (Based on Surveillance Capsule Data)

Parameter Values Operating Time 12 EFPY ,

Location *) 1/4T ART 3/4T ART Chemistry Factor, CF ( F) 16.7 16.7 i

Fluence (f), n/cm 2 4.95x10'8 1.78x10 (E>l.0 Mev)(*)

Fluence Factor, FF 0.804 0.542 ARTNnr= CFxFF('F) 13.43 9.05 Initial RT wor,,1(*F) 40 40 Margin, M('F) 13.43 9.05 ART = 1+(CF'FF)+M, *F 66,9 58.1 per RG 1.99, Revision 2 (a) Fluence, f,is based upon f,wr(E>l.0 Mev) = 1.100x10" at 16 EFPY, WCAP 14228 (Reference 3).

(b) The Braidwood Unit 2 reactor vessel wall thickness is 8.5 inches at the beltline region.

15

BRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT ,

Table 4.5 RTns Values for Braidwood Unit 2 for 32 EFPY '

CF p.) ppm M RTNoT(u) . ARTns RTns Material (*F) ('" (*F) ('F) ('F)

Upper Shell Forging - 20.0- 7199 1.214 '

.. -30 24.28 18.6 MK 24 3 Lower Shell Forging - 37.0. '..199 1.214 34.0 -30 44.92 48.9 Using Suneillance Capsule Data 13.3 2.199 1.214 34.0") -30 16.15 20.2 Circumferential Weld 41.0 2.199 1.214 49.77 40 49.77 139.5 Metal WF562 Using Surveillance 16.7 2.199 1.214 20.27 40 20.27 80.5 Capsule Data")

(a) 2.199x10" n/cm 2(E>l.0 Mev) for 32 EFPY from Braidwood 2 PTS report WCAP-14229 (Reference 8)

(b) FF (Fluence Factor) = fg2smos o (c) Calculated using CF based on surveillance capsule data per RG 1.99, Position 2 (Reference 11)

(d) Double margin is used here due to the base metal surveillance capsule data exceeding the one sigma criteria from the credibility evaluation. See WCAP-14824, Rev. 2 (Reference 2).

16

. BRAIDWOODS UNIT 2;

PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.6 -  :

~

RTns Values for Braidwood Unit 2 for 48 EFPY CF . p.) - ppm M_ RTwonu) 'ARTns .RTns  :

- Material - (*F); ('F)- ('F) ('F) (*F)

Upper Shell Forging - 20.0- 3.298 1.313 - 26.26 . -30 26.26- 22.5-Lower Shell Forging 37.0- 3.298 1.313 34.0 -30 48.58- 52.6 Using Surveillance - -

13.3 3.298 1.313 34.0 * - -30 17.46- 21.5 Capsule Data")

- Circumferential Weld ,1.0 3.298 1.313 53.83 40 -- 53.83 -147.7 Metal WF562 Using Surveillance 16.7- 3.298 1.313 21.93 40L 21.93 83.9-Capsule Data")

(a) 3.298x10 n/cm2(E>l.0 Mev) for 48 EFPY froni Braidwood 2 PTS report WCAP-14229 (Reference 8).

(b) FF (Fluence Factor) = fg2:4to ios o (c) Calculated using a CF based on surveillance capsule data per RG 1.99. Position 2 (Reference 11).

(d) Double margin is used here due to the base metal surveillance capsule data exceeding the one sigma i- criteria from the credibility evaluation. See WCAP-14824, Rev. 2 (Reference 2).

l I

1 17-g

} YrPM.- p y-.fbg gi 9 Py ad m.y g-P ,

t ' - + - 're-- + F

BRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

5.0 References
1. Andracheck, J.D., et al., WCAP-14040-A, " Methodology used oclop Cold Overpressure / Mitigating System Setpoints and RCS Heatup ac widown Limit Curves," Revision 2, January 1996.
2. Laubham, T.A., et al., WCAP-14824," Byron Unit 1 Heatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Byron &

Braidwood," Revision 2, November 1997 and Errata Sheets (Westinghouse Letter CAE-97-220, CCE-97-304 and Westinghouse Letter CAE-97-233, CCE-97-316).

3. Peter, P.A., et al., WCAP-14228," Analysis of Capsule X from the Commomvealth Edison Company Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program,"

March 1995.

4. Terek, E., et al., WCAP-12845, " Analysis of Capsule U from the Commonwealth Edison Company Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program,"

March 1991.

5. Westinghouse Letter to Commonwealth Edison Company, CCE-96-104,"Braidwood Unit 2 LTOPS Setpoints Based on 16 EFPY P/T Limits," January -?4,1996.
6. Singer, L.R., WCAP-11188," Commonwealth Edison Company, Braidwood Station Unit 2 Reactor Vessel Surveillance Program," December 1986.
7. Laubham, T. J., WCAP-14970,"Braidwood Unit 2 Heatup and Cooldown Limit Curves for Nonnal Operation," October 1997 and Errata Sheets (Westinghouse Letter CAE-91-210, CCE-97 289 and Westinghouse Letter CAE-97-232, CCE-97-315).
8. Peter, P.A., WCAP-14229," Evaluation of Pressurized Thermal Shock for Braidwood Unit 2," March 1995.
9. Lippencott, E.P. WCAP-14044," Westinghouse Surveillance Capsule Neutron Fluence Reevaluation," April 1994.
10. -10 CFR 50.61," Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," (PTS Rule) January 18,1996.

I 1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, " Radiation Embrittlement of Reactor Vessel Materials," Revision 2, May 1988.

12. Peter, P.A., WCAP-14243,"Braidwood Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," March 1995.

References (Continued) 18

BRAIDWOOD - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT ~

13. Comed Calculation BRW-96-%61/BYR 96-293," Channel Accuracy for Power Operated Relief Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit 2 Original Steam Generators)," Revision 0.
14. Westinghouse Letter to Commonwealth Edison Company,- CCE 97-278, " Comed Braidwood Unit 2 COMMS Setpoint for 12 EFPY," October 23,1997.

-15. Westinghouse Letter to Commonwealth Edison Company, CAE-97-211, CCE-97 290,

" Comed Byron and Braidwood Units 1 and 2 ATmetal Evaluation for Commonwealth Edison," November 7,1997.

19 i

l HRAIDWOOD - UNIT 2 l PRESSURE AND TEMPERATURE LIMITS REPORT I

l l

i ATTACIIMENT 1 WCAP-14824, REVISION 2, HYRON UNIT 1 IIEATUP AND COOLDOWN LIMIT CURVES FOR NORMAL OPERATION AND SURVEILLANCE WELD METAL INTEGRATION FOR HYRON AND BRAIDWOOD l

20

ATTACIIMENT D FTI LETTER INS-57-2526, JUNE 30,1997 FTI LETTER INS-97-4954, DECEMBER 17,1997 i

k:nla.bytm-d egrpptrrai ex:26

('

1

mm F rewuotooics R AM ATO M E June 30,- 1997 INS 97 2526 Integrated Nuclest Services To: B&W Owners Group Reactor Vessel Working Group Mr. R. E. Jaquin - Rochester Gas and Electric Mr P. S. Askins - Tennessee Valley Authority Gentlemen:

The NRC performed an inspection at Framatome Technologies, Inc. (FTI) on May 19-21,1997 to review records pertaining to the chemical composition (copper and nickel contents) of automatic submerged-arc welds in reactor vessels fabricated by Babcock & Wilcox. Prior to the inspection.

the staff requested that FTI provide chemical composition data for the reactor vessel and surveillance welds fabricated with copper coated weld wire and Linde 80 flux. During the inspection, FTI presented the staff with the available information including additional chemical composition dua that had not been previously reponed in FTI reports B AW-1500 and BAW-2121P. Subsequently, the staff requested that FTl also provide all avadable chemical composition data for welds fhbricated with noncopper coated weld wire and Linde to flux.~

During the exit meeting, FTI committed to compile all of the chemical composition data, provide references to establish traceability, assess the data, and notify the plant owners of the results.

Attached are summary tables of the chemical composition assessments for the Linde 80 weld metals as reported to the NRC. The chemical composition data were presented using three different assessments; (1) currently reported best-estimate values, (2) best-estimate values based on total population of all credible data, and (3) coil to-coil weighted average for weld copper contents. Review of the data assessments indicates that weld composition estimates prior to the inspection are conservative for most of the wire heats. For the copper coated wire heats where the estimates are nonconservative, the efects are inconsequential (i e., greater by only 0.01 wt%).

Should you have any questions regarding this inspection or the information provided to the NRC, please feel free to call me at 804/832-2783 or Matt DeVan at 804/832-3160.

Sincerely, D. L. Howell Project Manager B&W Owners Group Management DLH/mel Attachment 3315 Old Forest Road. PO. Bcx 10935, Lynchburg, VA 24500 o935 Telephone: 804 832 3000 Fax: 804-832 3663 Internet: http1/www.framatech.com l

}

t

. Reactor V-1 Working Groun i
R. W. Clark - - Entergy Operations,Inc.

- Commonwealth Edison Company'-

T. D. Spry :-

- W. F. Brady. _ .  : - Duke Power Company D. N. Miskjewicz i - Florida Power Corporation S. A Collard - Florida Power & Light Company _ . ,

' G. L Lehmann - GPU Nuclear, Inc.-

K. C. Prasad = - ToledoEdison Company i

- Virginia Power' J. R. Harrell - ,

- Wisconsin Electric Power Company J. R. Pfefferle c: B. J. Elliot - NRC-J. H. Taylor - FTI/OF56 e

4 h

9 s

, - ., , v -. ,# .~ y .._, . _ -_ m

Chemical Composition Data for Linde 80 welds Fabricated With Copper Confed Weld Wires

.==n.._.., ~

- , , - , - - . . ~ .

ent5: d7 7Mjysst.Estimaien .. i.iBd6E h -

f5?2iIdN.7 NUsiEMM40$h EBes is33iiiE P M M 5sDjk 4*. g g m: n/s..:

C2EU.E Hi%i.EE$ihifisi

~

if-i. @t-EstiFnit'ii *: -l~

v - myc .s =shh~s a.. Ag!w.-. ~.. ::.. . ..m~ m mmmama.

[ Weld..:W....ii.c.s 1

ageed v -

.: m= ;;;K

- -t..s.i.;.(.cy h w;tHiii:WesEF,-;2c r:=. a.

qqd[ gg n .:.

,g.33:g,:

, 7 gig 7gggg 299L44 Surry-1, TM1 1, 0.35 0.65 less cque.1 less ONS 1, ONS-2, Dresden 3 72105 CR-3, ONS 3, 0.35 0.59 less less less TMI-1, Zion 1, Zion 2, Turkey Point-4, 71249 R.C. Ginna, 0.26 0.61 less equal less Point Beach.1, Turkey Point-3.

Turkey Point 4, ONS 1, CR-3, Zion-1, Zion 2, Dresden-2 61782 R.E. Ginna, 0.25 0.56 less less less Point Beach-1, ONS-1 72445 ONS-1, Sury-1, 0.21 0.59 greater by less greater by Surry 2, 0.01 wt% 0.01 wt%

Quad Cities 1 405L44 ANO 1, ONS-2, 0.31 0.59 less less less Zion-1, Browns Ferty 1, Quad Cities-1 72442 Point Beach-2, 0.24 0.60 equal equal greater by Turkey Point-3, 0.01 wt%

Turkey Point-4, ONS-3 821T44 ANO-1, DB-1, 0.24 0.63 equal equal greater by ONS-3, Zion 2 0.01 wt%

8T1554 Surry 1, TMI-1, 0.18 0.63 less less less CR-3 72102 Zion-2 0.23 0.63 less less less ST3914 DB-1 0.18 0.64 equal equal equal T29744 DB-1 0.29 0.68 1-rs equal less

k.fhkIhhhhhh 4 - MMNhYs I'NbMNNh IMDkkN$fhk h"CBJt&do5i ht #sttmate - :TotafP6pulation -

M Ib- .+T

' .. t qyii . ,.1,m- >na ca - .:- a g :m: a .~- -zw ,w a. a ga-.,

gatstn ttam-ng

'fMEM1Tb.f;Q he,ian-M.,E_,:AyWeissB'v~L m>."yG1f,u.;

i n rsMWg ~1

. zu& s a.. "FF% W ;W ST1762 ONS-1, CR 3, 0.20 0.55- less equal less Point Beach-1, Surty 2, Zion 1,

'IMI 1, _ ANO 1 IP0962 ONS-1 0.21 0.64 equal equal equal IP0661 Point Beach 1, 0.19 0.63 less greater less Dresden-2 by 0.01 wt%

IP0815 Point Beach 1, 0.17 0.52 equal equal equal I Dresden-2 -_ ,

1 l

l

I l

Chemical Composition Data for Linde 80 Welds ,

Fabricated with Non Copper-Coated Weld Wires i I

m w r .- ,_.

,ik,p. . .

ui: @ b = M F.4smm:sstw.,,.*$f--

x aM grgg@tunMgur }m ngw*53ji;M:! -

GEME3!EdISEi!Ndf$$@$@~d i?dotalT6fnitiU6hJiQ E$if.Td didWdii :n:tCu. :6.t .,..

n .s. .t..-i.

.F*iit{n.:ca:.h ..i.

ru. ;i'2'

' . n"xxit w Z:

%e.,

'i x

r Hj q=j Mea:s:R-m.$

s

%AG.W8g.5...@...;

lltm.~. w g

??WenehdW .15FMt%y,,;jfy;Wi%' - w 3;5 5.. . #._h.t 442002 Byron-1, Byron.2 0.029 0.680 0.059 442011 Braidwood 1, 0.033 0.688 0.032 Braidwood-2, Byron-1, Byron-2 H4498 Braidwood 1, 0.042 0.460 0.042 B_taidwood 2 31401 Braidwood 1, 0.193 0.576 0.193 Byron 1, Byron.2 1084-18 Braidwood 2 0.038 0.600 0.038

I M F R AM ATO M E TtCHNOL001Es

' December 17,1997

INS-97-4954 Mr. T. D. Spry bc
KE Moore /OF50 Commonwealth Edison Company LB Gross /OF50 Opus West III- Suite 400 KK Yoon/OF50 1400 Opus Place hU DeVan/OF50 Downen Grove,IL 60515 WA PavinicWKnox.

Subject:

Weld Wire Data  :

i

Reference:

FTI Letter INS-97-2526 dated June 30,1997

Enclosure:

Low Copper Wald Wire Cheddstry Data- Byron 1,2 .

Dear Tom:

The reference letter outlines the results of the' NRC inspections of reactor vessel weld chemistry data performed at Framatome Technologies on May 19-20,1997.

The enclosure summarizes all of the low copper weld wire chemistry data applicable to B) Ton 1 and 2 that was provided to the NRC during the inspection.

Ifyou should require additional information, hicase feel free to call me at 804/832-3293 or Matt DeVan at 804/832-3160.

' Sincerely, D. L. Howell Project Manager B&W Owners Group Management DLH/mcl Enclosure 3315 Old Forest Road P.O. Box 10935, Lynchburg, VA 24506-0935 Telephone; 804 832 3000 Fax: 804-832 3663 Intemet. http //w,w.framatech.com

, I 4

Copper end NIchel Contos.t BeetEstimate Vehme (Total Popuistion including AN Credible Oste) so< ion copper v; eld Wires Fatwketed WIm Unde 80 Fhm

- + - ,- ,.- -

rr m 7 g r .- -

t - .

7

, ; , *} 4-N .'. i ' - , .

. g ., , .-

. .: +. .; , .:.. .

Low Copper Wokf Wkes 442002 80/82 0.029 0.019 0.000 0.053 Best-eshmete copper and ndsel contents obtained imm mean of evaEst#e data.

442011 85/SS 0.033 0.003 0.888 0.039 Best<mtimede copper eruf nichel contents obtained imm mean of awaBable data.

1 f44498 2/2 0.042 0.012 0.400 0.057 8est<pshmets copper and nicieel contents obesined from mean of evenable data.

1 31401 5/5 -0.193 0.G24 0.578 0.000, Boot. estimate copper and nicieel cordents ottained fmm mean of available data.

1064-18 1/1 0.038 -

0.000 - Best-est!rnate copper and niclest contents obtahed from mean of awn!!able data. '

i, l

[

~

Page 1

Mean cnd Standard Devitti:n of W:Id Wire Sources  !

l 442002 WF 336 8873 WO 3 0.028 0.603 0.004 0.127 0.059 0 626 l BY1 RVSP 21 0.022 0.600 0.002 0.023 Rod Robin 19/21 0.031 0.656 0.010 0.036 l l

WF-407 8968 WQ 2 0.049 0.600 0.027 0.170 WF 421 8968 WO 1 0.114 0.540 - --

WF 446 8064 WQ 1 0.148 0.600 - -

WF-447 8064 WQ 2 0.066 0.620 0.004 0.000 BY2 RVSP 31 0.023 0.712 0.002 0.028 442011 WF 501 8086 WO 1 0.028 0.630 - - . 0.032 0.667 WF 562 8061 WQ :2 0.035 0.660 0.007 0.014 BRI RVSP @ 0.033 0.671 0.003 0.029 BR2 RVSP 32 0.033 0.706 0.003 0.038 H4496 WF 610 0862 WQ 1 0.050 0.420 - - 0.042 0.460 WF 646 0261 WQ 1 0.033 0.500 - -

31401 WF 389 8968 WO '1 0.186 0.530 - --

0.193 0.576 WF 449 8064 WQ 1 0200 0.680 --- ----

WF-472 8086 WO 1 0.230 0.57 0 - -

WF-614 0852 WQ 1 0.180 0.540 --- -

WF 653 0261 WQ 1 0.190 0.560 - -

1084 18 WF-696 0261 WO 1 0.038 0.600 - -- --- 0.038 0.600 Page 1

I' Wold Wke Host 443RR a O Sowce Source Mean Sousco Std. Dev.

l Dela Plant ,

h Cu M Cu NI Qu Ni Nates Point ine Sousee WeM D FnaxLot Soum Mt. Vemon WQ -

^ -- - WF-336 8673 WeM QueMeetion Lab No.13792 0.081 0.400 1 -

Wold GuGIcation Sample 0.0N 0.650 0.027 0.675 0.004 0.035  ;

1 - - , WF-336 8673 2 - - WF-336 8673 Wold Que51 cation Sa.i fA. 0.34 0.700 Mt.Vemon WQ -

1 - - WF-407 8986 Wold 0ueWirasian I_ =h No.16115 0.0 5 0. m ,

Mt. Vemon WO -

4 WeM QumMication R mh No. 24023 0.000 0.720 Revised WO j 1 - - -- WF-407 P986 Mt. Vemon WO - _;

- -- - WF-421 8966 Wold Quelsemedan I ah No.18346 0.114 0.540 ,

1 ,

Mt. Vemon WO -

- - - WF-446 8064 Weld Quellficahon 8 =h No.17543 0.148 0.600 1

Mt. Vemon WD-

- - WF-447 8064 Wold Quellficallon 8 =h No.17544 O_ama 0.620 1

Mt. Vemon WO -

O_nna 0.620 Revised WO 1 - - WF-447 8064 Wald OusMication Lab No. 20389 RVSP Boseline Referenos-Sury. Weld Block Chenustry 0. M 0.710 '# CAP-9517 1 - BY1 WF-336 8673 CVN SpedE a

Reference:

i

' 0.669 0.001 - 0.025WCAP-11651 .;

BY1 WF-336 38L Surv. Wold Block O - AW-1 0.023 0.670 0.021 1e -  ;

' CVN Soecimen  ;

WF-336 8673 Sury. Wold Block O - AW-1 0.0 21 C.714 ib - BY1 CVN '.'pecimen WF-336 8650 Sury.Wald Block O - AW-2 0.021 0.741 f 2 - BY1 CvN Specimen Surv. Weld Block 10 - AW-3 0.023 0.713 a i 3 - BY1 WF 336 8650 CVN S$a. j BY1 WF-336 8650 Sury. Weld Block 10 - AW-4 0.021 0.714 4 - i

! CVN Specimen .

l BY1 WF-336 8650 Surv. Weld Brock ID - AW-5 0.020 0.704

} S -

CV N Sped.. .

BY1 WF-336 - 6873 Sury. Weld Block BD - AW-6 0.020 0.894 ,

6 -

CVNS m . .

7 - BY1 WF 336 8873 Suev. Weld Block ID - AW-7 0.ON 0.706 Pege 1  !

[

l _

Wold Wits Heat 442002 l Data Plant Soufce Source Mean Soup Std. Dev.

po;ni Loc. Souece W old O Flux Ld Source Refesence Cu M Cu N1 l Cu M Notes CVN Specimen 8 -

BYf WF-338 8873 Suw. Weld Block O - AW-8 0.021 0.677

! CVN Spedmen l

9e --- BY1 WF-336 887J Suw. Weld Block O - AW-9 0.022 0.885 CVN Specimen 9b - BY1 WF-336 8873 Sury.Wald Block ID - AW-9 0.033 'O.677 l CVN Spedmen 10 - BY1 WF-336 8873 Sury. Weld Block ID - AW-10 0.0 21 0.880 CVN Specimen 11 - BY1 WF-336 8873 Suw. Weld Block ID - AW-11 0.021 0.680 CVN Specimen 12 - BY1 WF-336 8873 Suw. Weld Block ID - AW-12 0.021 0.887 l

CVN Specirnen 13 - BY1 WF-336 8873 Suw. Weld Block ID - AW-13 0.024 0.877 CVN Specimen 14 - BY1 WF-338 8873 Suw. Weld Block ID - AW-14 0.023 0.697 CVN Specimen 15 - BY1 WF-33G 8873 Sury. Weld Block ID - AW-15 0.021 0.634 CVN Specimen  ; Reference-1 - BY1 WF-336 8873 Suw. Weld Block ID - AW-48 0.024 0.882 0.024 0.688 0.002 0.015 WCAP- 13880 CVN Specimen 2 - BY1 WF-336 8873 Sury. Weld Block ' ID - AW-60 0.022 0.878 CVN Specimen 3 - BY1 WF-336 8873 Sury. Weld Block ID - AW-57 0.025 0.705 RVSP BaseEne Reference-1 - BY2 WF-447 8064 Surv. Weld Block Chemistry 0.030 0.660 WCAP-10398 ,

CVN Specimen Reference-1 - BY2 WF-447 8064 Sury. Weld Block tD - YW-1 0.022 0.704 0.021 0.718 0.002 0.036 WCAP-12431 CVN Specimen .

2 - BY2 WF-447 8064 Sury. Wald Block ID - YW-2 0.020 0.681-CVN Specimen 3 -- BY2 WF-447 8064 Sury. Weld Block ID - YW-3 0.021 0.706 CVN Specinen 4 -- BY2 WF-447 8064 Surv. Weld B:ock ,lO I

- YW-4 0.020 0.897 Page 2

Weld Wire Heat 442002 Data Plant Souses Source Mean Souses Std. Dev.

Point Loc. Sousee WeldID Fha Let Source Refe'ence Cu Ni Cu Ni Cu '

Ni Notes l CVN Spect'non j 5 -

BY2 WF-447 8064 Sury. Weld B8cck ID - YW-5 0.01 9 0.668 l '

CVN Specimen l 8 -

BY2 WF-447 8064 Sury. Weld B:ock ID - YW-6 0.024 0.740 CVN Specimen 7 - BY2 WF-447 8064 Sury. Wold B!od IG - YW-7 0.022 0.759 CVN SpeckTien 8 - BY2 WF-447 8064 Sury. Weld Block 10 - YW-8 0.0 21 0.714 CVN Specimen 9 - BY2 WF-447 8064 Sury. Weld Block D - YW-9 0.020 0.678 CVN Specimen 10 -

BY2 WF-447 8064 Sury. Wald Block 10 - YW-10 0.020 0.695 CVN Specimen 11 -

BY2 WF-447 8064 Sury. Weld Block 0.01 9 J.680 ID - _YW-11 _

CVN Specimen 12- -

BY2 WF-447 8064 Sury. Weld Block ID - YW-12 0.021 0.744 CVN Specimen 13 -

BY2 WF-447 8064 Surv. Weld Block 10 - YW-13 0.023 0.736 CVN Specimen 94 - BY2 - WF-447 8064 Sury. Weld Block 10 - YW-14 0.022 0.771 CVN Spedrnen 15 - BY2 WF-447 8064 Sury. Weld Block ID - YW-15 0.024 0.785 CVN Specimen Referanosc 1 - BY2 WF-447 8064 Surv. Wald Block ID - YW-31 0.024 0.705 0.024 0.709 0.001 0.007 WCAP-14064 CVN Specimen 2 --- BY2 WF-447 8064 Sury. Wekt Block 10 - YW-32 0.023 0.706 CVN Specimen 3 - BY2 WF-447 8064 Sury.Wald Block : ID - YW-33 0.023 0.698 CVN Specanon j .

4 - BY2 WF-447 8064 Surv. Weld Block ID - YW-34 0.024 0.696 CVN Spedmen 5 - BY2 WF-447 8064 Sury. Weld Block ID - YW-35 0.023 0.711 CVN Specimen 6 -

BY2 WF-447 8064 Sury. Weld Block ID - YW-36 0.024 0.708

  • f Page 3

_ . ~. . .. _ _ _ _ _

t I Date Plant Somos Sorce Mean So w ce Sai Dev. 1

Point Loc. Sowce WaldID Flux W Sousee Refesence Cu Ni Cu I M1 Cu Ni Noems CVN Specimen ,

7 - SY2 WF-447 8064 Sww.Wald Block 10 - YW-37 0434 0.716 i CVN Specimen 8 -

BY2 WF-447 8064 Sww. Wold Block ID -YW 36 0.34 0.715 -

l CVN Specimen 9 -

BY2 W/-447 8064 Sww.Wald Block D - YW-30 0.94 0.707 t

CVN Specimen 10 -

BY2 WF-447 8064 Swv. Weld Block ID-YW40 0.(94 0.720 t

CVN Specimen i 11 -

BY2 WF-447 8064- Sww. Wold Block ID - YW-41 0.(34 0.717 CVN Specimen 12 - BY2 WF-447 8064 Swv. Weld Nr* O - YW-42 0.034 0.711 CVN Specimen l 13 - BY2 WF-447 8064 Swv. Wald Brock 10 - YW-43 0.W4 0.706  ;

CVN Specimen j 14 -

BY2 WF-447 8064 Sww. Wold Block ID - YW-44 0.034 0.707 CVN Specimen  !

15 -

'BY2 WF 447 8064 Surv. Weld Block 10 - YW-45 0.03 0.717  !

Round Robin Sarnple  !'

ut. vemon analysis - .

'1 Top - WF-336 8673 -

Lab No. 26770 0.O N 0.680 0.029 0.678 0.004 0.013 Round Robin Sample 2 Top - WF-336 8673 - Mt. Vemon analysie 0.031 0.000 i Round Robin Sampio l Mt. Vemon analysis -

l 3 Bem - WF-336 8673 -

Lab No. 26771 0.000 0 690 Round Robin Sample

! 4 Btm .. WF-336 8673 -

Mt. Vemon anefysis ' O.033 0.000 Round Robin Sample .

1' Top - WF-336 8673 - Barberton enefysis 0.03 0.800 0.030 0.655 0.001 0.007 Round Robin Sarnple 2 Btm --

WF-336 8673 -

Bewberton analysis 0.020 0.650 Round Robin Sample .

1 Top -- WF-336 6873 - LRC analyels 0.020 0.620 0.030 0.645 0.014 0.035 Page 4 i

I

Weid Wire Heat 44502 Data Piern Sousee Sowce Mean Source Sid. Dev.

Point Loc. Sowce Wold ID Flau tot Source Re%sence Cu Ni Cu a MI Cu N Notes Round Robin Sergie 2 Btrn - WF-336 8873 -

LRC anaWs 0.040 0.670 Round Robin Sample 1 -

- WF-336 8873 - LRC analysis 0.020 0.590 0.027 0.585 0.000 0.010 i

Round Robin Saniple 2 - -

WF-336 8873 - LWJ analysis 0.027 0.573 Round Robin Sample WF-336 LRC analysis 0.027 0.501 3 - -

88 ] -

Round Rath. Sample 1 Top - WF-336 8873 - LRC analysis 0.030 0.700 0.030 0.706 0.000 0.007 Round Robin Sample 2 Btm -

WF-336 8673 - LRC analysis 3.030 0.710

, Round Robin Sasgle 1 - - WF-336 8873 J&L SteelCo analysis 0.038 0.668 .

I IRound Roth Semple 1 - - WF-336 8873 - ORNL analyses 0.070 0.640 0.070 0.657 -

0.015 Round Robin Sample 2 Top -

WF-336 8873 - Y-12 anafysis <0.10 0.670 ,

Round Robin Sarmfe 3 Btm WF-3'40 8873 - Y-12 analysis <0.10 0.860 Round Robin Sample 1 - - WF-336 8873 - NBS analysis-WF338 0.030 0.673 0.028 0.674 0.001 0.005 Cu & Nimean of 4 analyses ,

NBS analysis -

2 --- - WF-336 3873 --

WF336 0.0G9 0.667 Cu & Ni snean of 4 anaiyses Round Robin Sampfe 3 - - WF-036 6873 - NBS analysis-WF336 0.020 0.677 Cu & Nirnean of 4 analyses Round Robin Sample .

WF-336 8873 NBS analysle-WF336 0.020 0.679 4 - - -

Cu & Ni mean of 4 analyses j Page5 1

'l Wekt Wire Host 4W11 Dels Plant Sousee Soeste Mean Seesce Sed. Dev.

Point Loc. Sowce Wald ID Flux Lot Sowoe Refesence CW M Cu NI Cu Ni Notes Mt. Vemcm WO -

~1 --- - WF-501 8086 Wold Quellficalson Lab No.20419 0. W 0.830 Mt.Vemon WO -

1 - -

WF-582' 8001 Wold Quel"ication Lab No.22544 0.030 0.650 i Mt. Vemon WQ -

1 - - WF-562 8081 Weld Quemicaton Lab No.22541 0.000 0.670 t RVSP BaseAr.e Reference-1 - BR1 WF-562 8061 Sury. Wold Block Chernistry 0.040 0.670 WCAP-0807 CVN Specimen

Reference:

1 -

BR1 WF402 8061 Sury. Wald Block ID - EW-1 0.034 0.723 0.033 0.685 0.002 0.034 WCAP-12685 l CVN Spedmen  ;

2 - BR1 WF-562 8061 Surv. Wald Block ID - EW-2 0.0 5 0.709 i CVN Specimen 3 - BR1 WF-562 8061 Sury. Wold Block D - EW-3 0.034 0.726 i i

CVN Specnnen 4 - BR1 WF-582 8061 Sury. Wold Block 10 - EW-4 0. 4 0.066 CVN Specimen 6 - BR1 WF-582 8061 Surv. Weld Block ID - EW-5 0.0 5 0.699 CVN Specimen 6 - BR1 WF-562 8061 Surv. Wald Block 10 - EW-6 0.005 0.751 CvN Specimen 7 - BR1 WF-562 8061 Sury. Wold Block 10 - EW-7 0.0 31 0.863 CVN Specimen 8 _-- BR1 WF-562 8061 Sury. Weld Block 10 - EW-8 0.0 M 0.673 ,

CVN SpecJmon 9 - BR1 WF-562 8061 Sury. Wald Blo$ 10 - EW-9 0.000 0.666 CVN Specimen 10 - BR1 WF-562 8061 Sury. Wold Block fD - EW-10 0.023 ' O.686 i CVN Specirmen .

I 11 -

BR1 WF-562 8061 Surv. Weld Block 10 - EW 11 0.034 0.616 CVN Specimen 12 - BR1 WFN 8061 Sury. Wold Block ID - EW 12 0.033 0.651 CVN Specinya:

13 - DR1 WF-562 8061 Surv. Wold B!ock 10 - EW-13 0.033 0.698 ,

Page 1

n

'  ?

..g L

a -

l 4

Wald Who Host 461 , 1 i

Date .

Plant .

3 Sousco LSomme Mean Sousco Std.Dev.

Potut Loc. Sossee W ald D FhetLet Snusco Refesence - Os M" Cu Ni Cu 78

Nesse 'l 1

3 . .

CVN Specimen .  !

j '14 -

BR1 WF-682 8081 Sury. Weed HIock O - EW naat o_atsst' ,

CVN W d

l. 15 - BR1' WF-882 8081 Burv. W6Jd Blodt 10 - EW-15 0.8 W 0.886 '

CVN Specirnen Roderence Sury. Wold Blodc BR1 WF-882 i 1 -

8061 ID - EW-48 0.439 0= 0.032 0.888 0.003  : 0.010 WCAP-14241 I  ;

CVN Spedmen . .

2 -- Sury. Wold Block

-BR1 WF-582 8081 O - EW-52 ' O.W L 0.647 l CVN Spedmen q: 3 - BR1 WF-582 8081 Sury. Wald INock O - EW-55 0. W 0.838

] -

CVN Specimen a

'4 -

BR1- WF-582 8081 Sury. Wakf Block 10 - EW-48 0.431 0.655 CVN Specimen 5 -

BR1 WF-882 8061 Sury. Wold Block ID - EW-40 -

0.001 0.850 L -

CVN Specimen F

6 --

BR1 WF-582 8081 Surv. Wold Block O - EW-50 0.003 0.881 .

CVN Spoolmen 7' - BR1 WF-582 8081 Sury.Wald Blodt 0 - EW-51 0.0M 0.887 -t i

CVN %+f-:, -

l 8 - BR1 WF-582 8061 Surv. Wold Block ID - EW-53 0.8W 0.648  !

CVN Specirnen 9 - BR1 WF-582 ~8061 Sury. Wold Blodt ID - EW-54 0.d F 0.644  !

CVN Spedmen -j i 10 -

-BR1 WF-882 8081 Sury. Wold Block O - EW-58 0.tSt 0.888 I i CVN -W ,

L 11 - BR1 WF-882 - '8061 Sury. Wold Block O - EW-57 ~0.04 ' 0.858  !

i CVN W '

12 --- BR1 WF-582 8081 Sury. Wold Block 60 - EW-58 U.000 0.658

. CVN C ::: L;. -

13 - BR1 WF-582 8081 Sury. Wald Block ID - EW-50 0.000 0.671 1 CVN Spedmen 14 - BR1 WF-582 8061 Sury. Wold Block ID - EW-60 0.04 0.867 RVSPB 6 cleference:  :

1 -

BR2 WF-582 8061 Sury. Wold Blodt Chemistry 0.000 0.640 WCAP-11188 j CVN Spectruen

Reference:

l 1 ---

BR2 WF-582 -

8061 Sury. Weld Block 10 - FW-1 -0.05 0.704 0.0$? . 0.699 0.003 0.043 WCAP-12845 '  !

-i Page 2

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