ML20212P040

From kanterella
Jump to navigation Jump to search
Assumptions & Calculation of Resistor Temp for Pressurized Thermal Shock at End of License for Matls in Calvert Cliffs Units 1 & 2 Reactor Vessel Beltline Region
ML20212P040
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/16/1986
From: Pond R, David Wright
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20212P031 List:
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8609020151
Download: ML20212P040 (28)
v • d • e


Text

f

+

t Assumptions and Calculation of RT m

at End of Licens.e for Materials in Calvert Cliffs Units 1 and 2 Reactor Vessel Baltilne Region

~

Principal Investigator D. A. Wright a

Metallurgical Engineer Reviewe r R. B. Pond, Jr.

Principal Meta 11ergist Baltimore Gas & Electric ME&AU Job Number - MR-85-170 December 23, 1985 1 .

t

! B609020151 060029 ADOCK 0D000317 PDR P PDR

)

4

  • i Rev. O January 16. 1986 i

r E

N l

In order to comply with the July,1985 ammendments and additions to 10 CFR Part 50.34 and 50.61, the Baltimore Gas & Electric Company has compiled the necessary information to perform the Pressurized Thermal Shock (PTS) rule calculations for ,

RT These calculations indicate that the materials in the beltline region of PTS.

Calvert Cliffs Unit 1 and 2 will not exceed the PTS screening criteria prior to the

! end of their licenses.

I i

l l

1 i

I t

j i

i j (.-

i .

1 e

i i

r I

f 1

t a '

t Rev 0 January 15, 1986 j

( ILLUSTRATIONS FICURE 1-1 Calvert Cliffs Reactor Vessel Map 2-1 Correspondence between Nl content of the weld wire and NL content of the deposited weld metal.

2-2 Lack of correspondence between cu content of the weld wire and Cu content of deposited weld metal TABLES E

TAB L_E, 1-1 Calvert Cliffs Unit No.1 Reactor Vessel Baltilne Materials 1-2 Calvert Cliffs Unit No. 2 Reactor Vessel Baltilne Materials 4-3 Csivert Cilffs Unit No.1 Reactor Vessel Baltilne Material RTPTS 4-4 Calvert Cliffs Unit No. 2 Reactor Vessel Baltilne Matarlai RTPTS 11 Rev 0 January 15, 1986

- - _ _ - -- _. . . _ - ~ . .

( TABLE OF COIrrElfrS 1.0 History 2.0 Background Information on Beltilne Materials 2.1 Chemical Composition
2.2 Hechanical Properties 3.0 Determination of Chemical Composition and Mechanical Properties i 3.1 Chemical Composition Determination l

3.2 Hechanical Properties Determination j 4.0 Determination of RT PTS 5.0 References ]

I Appendix A Chemical Composition of Weldments in the Baltilne [

Region of Calvert Cilf fs Reactor Vessel Units 1 and 2 Appendlx B Maximum Fluence Predictions for Calvert Cliffs Units

, 1 and 2 at End of License s

l l ,

i j -

i j

1 I

e' j lli- Rav 0 January 15, 1986 I

( l.0 History The reactor vessels for Calvert Cliffs Unit No. I and 2 were fabricated by Combustion Engineering (CE) at Chattanooga Works, Tennest.ee for Combustion Engineering Power System Division in Windsor, Connecticut. The vessels are fabricated of formed and welded SA 533 Grade B Class 1 plates. This is the normal fabrication technique for Chattanooga facility. CE has used several different welding procedures at different periods of time and for the Calvert Cliff vessels a submerged are welding process was employed using a Mil B-4 Modified (Mn-Mo-NL) wire with nickel in the range of 0.6 to 1.1 wt%. The Mil B-4 Modified (Mn-Mo-NL) welds were produced with either a Linde 1092, 0091, or 124 flux. Welding procedures include both a single and tandem arc procedure.

A list of the reactor vessel beltline materials for Calvert C1Lifs Unit No. 1 and 2 are shown in Table No. 1-1 sud 1-2 respectively. The location of these materials with respect to the core beltline region are shown in Figure No. 1-1.

TABLE MO. 1-1 CALVEET CLIFFS UNIT NO. 1 REACTOR VESSEL BELTLINE MATERIALS WELD MATERIALS (1.):

ID TYPE WIRE (S) FLUE TYPE LOT NO.

2-203- Longitudinal 20291 1092 3833 A,B,C Tandem Arc 12008 3-203- Longitudinal 33A277 0091 3922

' (i A,B,C Tandem Arc 9-203 Girth 21935 1092 3869 Single Arc PLATE MATERIALS (2.)a ID LOCATION D-7206- Intermediate Shell Piste 1,2,3 D-7207- Lower Shn11 Plate 1,2,3

1. All weld wire was Mit B-4 modified (Ni-Mn-Mo).
2. All plate material was provided according to ASME SA 533 Grade B Class 1 specification.

i r

1-1 Rev. O January 15, 1986

( TABLE NO. 1-2: CALVERT CLIFFS UNIT No. 2 REACTOR VESSEL BELTLINE MATERIALS WELD MATERIALS (1.):

! ID TYPE WIRE (S) FLUX TYPE LOT EO.

2-203- Longitudinal 8746 124 3878 A,B,C Tandem Arc 3-203- Longitudinal 33A277 0091 3922 A,B,C Tandem Arc 9-203 Girth 10137 0091 3999 Single Arc PIATE MATERIALS (2.):

ID LOCATION D-8906- Intermodlato Shall Plato ,

1,2,3 D-8907- Lower Shall Plato

.1,2,3 1

1. All vold wire was !!Il B-4 modiflod (N1-!!n-Mo).
2. All plato material was provided according to ASME SA 533 Crado B Claes 1 speciffcation. -

Outlet Inlet inlet Outlet inlet Inlet Oattet

} 20 g c0 :......................................................................

$ 100 .

h y ...... ..::................... . . . . . .Q . . . . . .C.o.r.g . . . . . .................'.

l

  • 180 -

r 9 203

~

  • . ............. 2 I A '

h220

.2 . , , ,

l ,

l ,

200 () 90 100 270 WD

( Azimuthal Location (dogrees) i Figure 1-1: Calvert Cliffe Ro.netor Prosauro Vascal Hap l-2 Rev. O January 15, 1986

l 2.0 Background Information on Baltilne Materials j 2.1 Plates 1

The lower and intermediate shell courses of the Calvert Cliffs reactor vessels receive the highest fluences in the entire vessel and therefore specimens from these materials were used for surveillance. Selection of

( the plate material was based on Nil Ductility Transition Tersperature 1 (NDTT) and Charpy V-notch impact curves. The six plate sections used to

! fabricate the beltilne region have been well characterized with respect to chemistry and mechanical properties by Combustion Cngineering (Referencos l 1 and 2).

l 2.2 Welds I

The chemical compositions of the welds were not readily available with the exception of tite wire / flux combinations used in the Calvert Cliffs surveillance programs (Reference 3). Mechanical properties of the wire / flux combinations used in the surveillance programs were well l characterized.

Recognizing the need for more information on chemical composition, BG&E contracted CE in late 1981 to perform a search of their records at i Chattanooga. These results were issued in a transmittal from Kruse (CE) l to Titiand (BC&E) dated January 11,1982 (Reference 4). Included in this l were available wire chemistries and chemical analysis of weld deposits for l . certain wire / flux combinations. Although this information did not provide l

( data necessary for all the welds it was helpful in providing insisht into the relationship between weld wire chemistries and weld deposit chemistries. The general conclusions that have been drawn from the available data are the following (References 4 and 5):

1. In general, the flux 1.ot No. has 11ttia or no effect on the deposit .

analysis with respect to copper and nickel contents.

2. The nicket content of the wiro la very similar to that of the weld deposit (See Figure No. 2).
3. The copper content of the wold deposit is not accurately reflected by the copper content of the wire (See Figure No. 3). It is generally higher in the weld deposit than in the weld wire.

l

4. A review of the data indicated that the composition of a weld deposit l

made with two dif ferent wires (Tanden Arc Process) can be nacimated accurately by an arithemite average of deposit chemistries of Individual wiros. For a more detalled explanation see Reference 5.

EpRt performed a revlew of the material survel11ance data base MATSURV (Re ferenco 6) to (dontify that wold wire used in the Calvert Cliffs beltilna welds was also used in the fabrication of the surveillanco blocks for the Cooper Station BWR. The Cooper Station reactor was produced by l l CE. Under EpRI contract RP 2180-5, the General Electric Company generated f chnmical composition and mechanical properties data on the Cooper

\. weldments removed from archlval sections at CE Nuclear Center at Vallecitos, California.

2-1 Rev. 0 Jaquary 15, 1986 i

is~-+

4 In early 1983, BG&E contracted with CE to compile and reproduco re which document the materials of the Calvert Cliffs Units 1 and 2 rc vessels (Reference 7 and 8).

EPRI through cooperation with utilities has compiled a reac tor '

aurvelliance program data base (Referenco 9). The data base c o-Information on irradiated and unirradiated material from survel e programs. A search of this data base in January 1986 revealed thac a particular wiro/ flux combination used in the Clavert Cilffs boltilne welds was also used in the fabrication of survelliance blocks for Duke Tc 2r Company's William B. McCuiro Unit No. 1. Sinco, this material was used in the production of surveillance blocks the chemical composition and mechanical proporties are both wall charaterized (Reference 10).

w i i i i i b

2

(" f1.0 t'

g*

[ 0.8 -

a

, . 1 g 0.6 - -

, u s "c 1:1 3, 0.4 - - i 8 .

E 0.2 - . --

0.0 , , , , ,

0.0 0.2 0.4 0.6 0.8 1.0 1,1 NI Content (Wtt) Wire Chemistry Figure 2-1

( Correspondance Botwoon Ni Content of the Wold Wire and Ni Content of the Deposited Wold Hotal (Reference 5) 9.9 cm. n ,........,, enea

> i i i i i o

b0.3 - .

5 8 j .

m

    • o#

0E.0.2 - O o 0 .

o a

7 g 1:1

., 0.1 E

c g . .

O 0 .0 , , , , ,

0.0 0.1 0.2 0.3 Cu Content (Wtt) Wire Chemistry Figuro 2-2: Lack of Correspondence Bctwoon Cu Conte.nt of the Wald Wlre and Cu Content of Deposited Weld Metal (Reference 5) e t

.. m .

1-1 n o., n , , ,, . . . . . . i s snea

e

( 3.0 Determination of Chemical Composition and Mechanical Properties 3.1 Chemics 1 Composition The information corpiled in Section 2.0 from various sources has beau used to determino the chemical composition of materials in the Calvert Cliffs reactor vessels beltline regions. The following guidelines were used to determine the chemical composition of the welds (See Appendix A):

1. Copper content for a particular wire / flux combination was determined from deposited weld metal chemical analyses using the same wire / flux combination (the flux Lot No. may vary).
2. Nickel content of a wellment was determined from both veld wire chemical analyses and deposited weld metal chemical analyses.
3. For Tandem arc processes the chemical composition from the single wires were averaged to decermine the chemical composition of the weldment when t.sndem deposit chemical analyses were not availabic.

Chemical compositions for the welds were determined in Appendix A by averaging the data compiled in accordance with the above guidelines. Note that in Appendix A the analysis numbers with an "R" as a prefix Indicates a weld wire chetalcal analysis and the analyses numbors with "D" as a

, prefix indicates a wold deposit chemical analysis. All remaining alloy

( determinations (surveillance capsula, EPRI, etc.) are also from weld deposit chemical analyses.

As previously mentioned chemical ' compositions of the plates were well documented in References 1 and 2.

. c 3.2 Mechanical Properties, Initial RT values for some of the woldments in the battilne rsglon of Calvert C1kfs reactor vessels were datorminal by measurements made in the Calvert Cliffs surveillance programs lir specific wLre/ flux combinations. Initial RT for wire / flux combinations in seme welds at Calvert Cilf fs was determYned f rom measurements made in the William B.

McCulre linit No. 1 Survel11ance Program. For all otheir wire / flux ,

combinations used, the generic mean value was assigned in accordance with 10 CFR Part 50.61.

As previously mentioned, the Initial RT NDT IO' th" P13888 I* "'II documented in Reference 1 and 2.

3-1 Rev. 0 ' January 15, 1986  ;

( 4.0 Determination of RTPTS '

Estimated chemistries from Appendix A were used in conjunction with predicted 32 EFPY fluences in Appendix B to calculate the RT at the expiration of the PTS operating licenses for Calvert Cliffs Unit 1 and 2 tn accordance with 10 CFR Part 50.61. Tables 4-1 and 4-2 provide a summary of estimated chemistries, initial RT ND and 32 EFPY RTPTS fr Calverr Cliffs Unit No. 1 and 2 respectively.T A review of the calculated RTp.pg vslues indicates that none of the unterials in the beltilne region of either Calvert Cliffs vessels will exceed the pressurized thermal shock screening criteria prior to expiration of their operting licenses.

TABLE NO. 4-1 CALVERT CLIFFS UNIT NO.1 REACTOR VESSEL BELTLINE MATERIAL RTygg (a)

ID Cu (w/o) Ni (w/o) INITIA1. RTNDT( F) 32 EFPY RTFTS( F) 2-203 -0.21(b) 0.87(b) -50.0(c) 238.0 A,B,C 3-203 -0.21(b) 0.69(b) -56.0(d) 223.0 A,B,C 9-203 0.23(b) 0.23(b) -80.0(e) 152.0

, D-7216-1 0.11(f) 0.55 ( f) 20.0(f) 167.0 D-7205-2 0.12(f) 0. 64( f) -30.0(f) 133.0 I

D-7206-3 0.12(f) 0.64( f) 10.0( f) 173.0 D-7206-1 0.13(f) 0. 54( f) 10.0(f) 177.0 .

D-7207-2 , 0.11( f) 0.56( f) -10. 0 ( f) 133.0 D-7207-3 0.11( f) 0.53(f) -20.0( f) 126.0

a. RTPTS calculated in accordance with 10CFR 50.61 using a 32 EFPY fluence of 5.373 X 10I9n/cm2 ,
b. See chemistry data In Appendlx for sources.
c. Davidson, J. A. and Yanicko. S.1., " Duke Power Company Wllliam B. McCulto Unit No. 1 Reactor Vessel Radiation Surveillance Program", WCAP-91995, November 1977
d. Coneric maan value,
c. Byrno S. T., Blomiller, E. 1. . and Rag 1, A., " Testing and Evaluation of Calvert Cliffs, Units I and 2 Reactor Vossal Haterials Irradiation Surveillance Program Baseline Samplos", Combustion Engineering, TR-ESS-001, January 31, 1975.

(~ f. " Summary Report on Hanufacture of Test Specimens and Assembly of Capsules For 1rradiation Surveillance of Calvert Cliffs Unit 1 Reactor Vessel Materials",

Combustion Engineering, CENPO-34, February 4,1972.

i 4-1 Rev. O January 15, 1986.

( TABLE NO. 4-2: CALVERT CLIFFS UNIT NO. 2 REACTOR VESSEL BELTLINE MATERIAL RTPTS (a)

ID Cu (w/o) Mi (w/o) 32 EFPY RT p.g.g(OF)

INITIAL RTNDT( F) 2-203- 0.12(b) 1.01(b) -56.0(c) 143.0 A,B,C 3-203 0.23(b) 0.23(b) -80.0(d) 151.0 A,B,C 9-203 0.22(b) 0.05(b) -60.0(d) 141.0 D-8906-1 0.15(e) 0.56(e) 10.0(e) 199.0 D-8906-2 0.11(e) 0.56(e) 10.0(e) 157.0 D-8906-3 0.14(e) 0.55(e) 5.0(e) 183.0 D-8907-1 0.15(e) 0.60(e) -8.0(e) 185.0 D-8907-2 0.14(e) 0.66(e) 10.0(e) 196.0 D-8907-3 0.11(c) 0.74(c) -16.0(e) 142.0

. a. RTPTS calculated in accordance with 10CFR 50.61 using a 32 EFPY fluence of 5.33 X 10I9n/cm2 ,

,b. See chemistry data in Appendix for sources. ,

c. Ceneric mean value.
d. Dyrne S. T., Binaller, E. L. and Ragl A. , " Testing and Evaluation of Calvert Clif fs, Units 1 and 2 Reactor Vessel Materials Irradiation Survalliance Program .

Baseline Samples", Combustion Engineering, TR-ESS-001, January 31, 1975.

e. "Surmnary Report on Manufactures of Test Specimens and Assembly of Capsules For Irradiation Surveillance of Calvert Clif fs Unit 2 Reactor Vessel Materlats",

Combustion Engineering, CENPD-48, February 4, 1972.

4-2 Rev. O January 15, 1986.

( 5.0 Re ferences 4 1. " Summary Report on Manufacture of Test Specimens and Assembly of Capusles For Irradiation Surveillance of Calvert Cliffs Unit 1 Reactor Vessel Materials",

Combustion Engineering, CENPD-34, February, 1972.

2. " Summary Report on Manuf acture of Test Specimens and Assembly of Capusies For Irradiation Surveillance of Calvert Cliffs Unit 2 Reactor Versel Materials",

Combustion Engineering, CENPD-48, February, 1972.

3. Byrne S. T. , Biemiller, E. L. and Ragi, A. , " Testing and Evaluation of Calvert Cliffs, Units 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples", Combustion Engineering, TR-ESS-001, January 31, 1975.
4. Letter from P. Kruse (CE) to L. E. Titland (BG&E), C-E Chatanooga Metallurgical Records Search, BC&C-10577-437, January 11, 1982.
5. Chexal, B., et al., "Calvert Cliffs 1 Reactor Vessel; Pressurized Thermal Shock Analysis for a Small Steam Line Break, EPRI Special Report NP-3752-Sr, November 4

1984.

6. Strosnider, J., et al., " Computerized Reactor Pressue Vessel Materials Information System", NUREG-0688, U.S. NRC, October 1980.

, 7. " Baltimore Cas and Electric Unit 1 Reactor Vessel Master Index with Welding Procedures, PQR's, Weld Materials Test Reports, and Base Materials Test

(- Reports", Combustion Engineering Contract No. 72167.

d. " Baltimore Gas and Electric Unit 2 Reactor Vessel Master Index with Welding Procedures, PQR's , Weld Materials Test Reports, and Base Materials Test Reports", Combustion Engineering Contract No. 73167. .
9. Old fleid ,, W. , et al., Nuclear Plant Iradiated Steel llandbook, EPRI Research Projects NP-1757-36, 1757-37, and 2455-5, September 1985.
10. Davidson, J. A. and Yanicko, S.E., " Duke Power Company William B. McCulte Unit NO. 1 Reactor Vessel Radiation Surveillance Program", WCAP-91995, November 1977.

k 5-1 Rev. O January 15, 1986

a f

Appendix A

, Chemical Composition of Weldments in the Beltline Region of Calvert Cliffs Reactor Vessels Units 1 and 2.

k Rev. O January 15, 1986

( WELD SEAM 2-203-A,B,C CCNPP UNIT NO. 1 WIRE (S) FLUK LOT NO. Cu (w/o) Ni (w/o) SOURCE / ANALYSIS NO.

12008 -- -- --

1.00 (1)/R-1990 20291 -- -- --

0.73 (1)/R-2248 20291 -- -- --

0.74 (1)/R-2293 12008 1092 3692 NA 1.01 (1)/D-4907 12008 1092 3869 0.22 NA (1)/D-7278 12008 1092 3869 0.20 NA (1)/D-7525 20291 1092 1833 0.21 0.74 (2,3)/NA 20291 1092 3833 0.22 0.73 (4)*/NA 12008 &

20291 1092 3854 0.21 0.88 (5,6)/NA CHEMISTRY CALCULATION Cu: ((0.22 + 0.20)/2 + (0.21 + 0.22)/2 +0.21)/3 = 0.21 w/o Cu Nis ((1.00 + 1.01)/2 + (0.73 + 0.74 + 0.74 + 0.73)/4 +0.88)/3 = 0.87 w/o Ni RSTIMATED CHEMISTRY-0.21 w/o Cu 0.87 w/o Ni

  • Average of five analyses.

NA - Not Available (1) Letter from P. Kruse (CE) to L. E. Titiand (BC&E), C-E Chattanooga Metallurgical Records Search, BG&E-10577-437, January 11, 1982.

(2) Letter from T. U. Manton (EPRI) to L. E. Titland, Attachment II: Cooper Station Surveillance Weld Chemistry, March 16, 1982.

(3) Strosnider, J., et al., " Computerized Reactor, Pressure Vessel Materials Information System", NUREG-0688, U.S. NRC, October 1980.

(4) Cooper Survelliance Weld Evaluation, General Electric, EPRI Contract RP2180-6, Aug. 1983.

(5) Old field, W., et al., Nuclear Plant Iradiated Steel Handbook, EPRI Research Projects NP-1757-36,1757-37, and 2455-5, September 1985.

(6) Davidson J. A. and Yanicko S.E., " Duke Power Company William B. McGuire Unit No.

1 Reacotr Vessel Radiation Survel11ance Program", WCAP-91995 November 1977.

A-1 Rev. O January 15, 1986

( WELD SKAM 3-203-A,B,C CCNPP UNIT NO.1 WIRE (S)- FLUX LOT NO. Cu (w/o) Ni (w/o) SOURCE / ANALYSIS NO.

21935 -- -- --

0.70 (1)/R-2546 21935 -- -- --

0.68 (1)/R-2503 21935 -- -- --

0.71 (1)/R-2495 21935 1092 3869 0.20 NA (1)/D-7279 21935 1092 3889 0.13 0.68 (1)/D-7569 21935 1092 3889 0.21 NA (1)/D-7524 CHEMISTRY CALCULATIONS Cu: (0.20 + 0.21)/2 = 0.21 w/o Cu*

Ni: (0.70 + 0.68 + 0.71~+ 0.68)/4 = 0.69 w/o Ni ESTIMATED CHEMISTRY 0.21 w/o Cu 0.69 w/o Ni

  • Note that one deposit analysis reported a copper content of 0.13 w/o. This was omitted from the chemistry calculation due to the non-conservative effects on estimating the average veld metal copper content with a sample size of three.

(1) Letter from P. Kruse (CE) to L. E. Titland (BG&E), C-E Chattanooga Metallurgical Records Search, BG&E-10577-437, January 11, 1982.

C.

A-2 Rev. O January 15, 1986

l

( UELD SEAM 9-203 CCNPF UNIT NO. 1 WIRE (E) FLUX LOT NO. Cu (w/o) Ni (w/o)

  • SOURCE / ANALYSIS NO.

33A277 0091 3922 0.30 NA (1)/D-7947 33A277 0091 3922 0.23- NA (1)/D-7948 33A277 0091 3977 0.23 NA , (1)/D-9217 33A277 0091 3922 0.24 0.'8 (2)/NA 33A277 0091 3922 0.14 0.27 (3)/NA CHEMISTRY CALCULATIONS Cu: (0.30 + 0.23 + 0.23 + 0.24 + 0.14)/5 = 0.23 w/o Cu Ni: (0.18 + 0.27)/2 = 0.23 w/o Ni ESTIMATED CHEMISTRY

( 0.23 w/o Cu 0.23 w/o Ni (1) " Baltimore Cas and Electric Unit 2 Reactor Vessel Master Index with Welding '

Procedures, PQR's, Weld Material Test Reports, and Base Material Test Reports",

Combustion Engineering Contract No. 73167. -

(2) Byrne S.'T., Biemiller, E. L. and Ragl A. , " Testing and Evaluation of Calvert Cliffs, Unit 1 and 2 Reactor Vessel Materials Irradiation Surveilla'nce Program Baseline Samples", Combustion Engineering, TR-ESS-001, January 31, 1975.

(3) Perrin, J. S., et al., "Calvert Cliffs Unit No. 2 Nuclear Plant Reactor Pressure Vessel Surveillance Program; Capsule 263", Final Report, Battelle Columbus Laboratories, December 15, 1980.

l I

A-3 Rev. O January 15, 1986

t

{s -

WELD SEAM 2-203-A,B,C CCNPP UNIT NO. 2 VIRE(S)~ FLUX LOT NO.- Cu (w/o) Ni (w/o) SOURCE / ANALYSIS NO.

- 8746 124 3878 0.12 NA- (1)/D-7314 ESTIMATED CHEMISTRY ,

0.12 w/o Cu 1.01 w/o Ni*

  • Ni is an upperbound estimate since no data could be found for this wire.

(1) " Baltimore Gas and Electric Unit 2 Reactor Vessel Master Index with Welding Procedures, PQR's, Weld Material Test Reports, and Base Material Test Reports",

Combustion Engineering Contract No. 73167.

(

A-4 Rev. O January 15, 1986.

WELD SEAM 3-203-A,B,C CCNPP UNIT NO. 2 UIRE(S) FLUX LOT NO. Cu (w/o) Ni (w/o) SOURCE / ANALYSIS NO.

32A277 0091 3922 0.30 NA (1)/D-7947 33A277 0091 3922 0.23 NA (1)/D-7948 33A277 0091 3977 0.23 NA (1)/D-9217 32A277 0091 3922 0.24 0.18 (2)/NA 33A277 0091 3922 0.14 0.27 (3)/NA CHEMISTRY CALCULATIONS Cu: = (0.30 + 0.23 + 0.23 + 0.24 + 0.14)/5 = 0.23 w/o Cu Ni: = (0.18 + 0.27)/2 = 0.23 w/o Ni ESTINATED CHEMISTRY ,

0.23 w/o Cu

(' O.23 w/o Ni (1) " Baltimore Gas and Electric Unit 2 Reactor Vessel Master Index with Welding Procedures, PQR's, Weld Material Test Reports, and Base Material Test Reports",

Combustica Engineering Contract No. 73167'.

(2) Byrne S.'T., Biemiller, E. L. and Ragl A. , " Testing and Evaluation of Calvert Cliffs, Unit 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples", Combustion Engineering, TR-ESS-001, January 31, 1975.

(3) Perrin, J. S., et al., "Calvert Cliffs Unit No. 2 Nuclear Plant Reactor Pressure Vessel Surveillance Program; Capsule 263", Final Report, Battelle Columbus Laboratories, December 15, 1980.

A-5 Rev. O January 15, 1986

a e

( WELD SEAM 9-203 CCNFP UNIT NO. 2 WIRE (S) FLUX LOT NO. du (w/o) Ni (w/o) SOURCE / ANALYSIS NO.

10137 0091 3999 0.23 NA (1)/D-10600 10137 OG91 3999 0.20 0.04 (2)/NA 10137 0091 3999 0.24 0.06 (3)/NA CHEMISTRY CALCULATIONS Cu: (0.23 + 0.20 + 0.24)/3 = 0.22 w/o Cu Ni: (0.04 + 0.06)/2 = 0.05 w/o Ni ESTIMATED CHEMISTRY 0.22 w/o'Cu '

0.05 w/o Ni

( (1) " Baltimore Gas and Electric Unit 2 Reactor Vessel Master Index with Welding Procedures, PQR's, Weld Material Test Reports, and Base Material Test Reports",

Combustion Engineering Contract No. 73167.

(2) Byrne S. T., Biemiller, E. L. and Ragl A. , " Testing and Evaluation of Calvert Cliffs, Unit 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples", Combustion Engineering, TR-ESS-001, January 31, 1975.

(3) Norris E. B., " Reactor Vessel Material Surveillance Program for Calvert Cliffs Unit 2 Analysis of 263 Capsule, Final Report, SwRI Project 06-7524, Southwest Research Institute, September, 1985.

c k ..

A-6 Rev. O January 15, 1986.

l Appendix B Maximum Fluence Predictions for Calvert Cliffs -

Units 1 and 2 at End of License.

k Rev. 0 January 15, 1986

'c NFM Calculation Package Cover Sheet 207TD8501 Number Fluence Calculatior.s 'or Units 1 and 2 j . Title

SUMMARY

Fluence Calculations were performed for Unit I and 2 based on peak assembly burnup for assembly Y-10. These calculations were made to support NRC rulemaking by January 26,1986.

Original Signed by: 3. E. Stanley Date: 12/2/85 IR: In accordance with the assumptions and conservatisms stated in this calculation package, this work presents reasonable and conservative estimates of EOL fluences at the critical weld for Units 1 and 2. Input data, general approach and arithmetic have been verified correct.

Original Signed by: D.S.'Elkins Date: 12/4/85 .

I Original Approved by: M. E. Bowman Date: 12/4/85 TRANSMITTALS

SUMMARY

4 f

i; -

i s

o s

?'

I k

4 9

4 4

+

- - -n,w.~... ,pp.,_,,.--,.,s-n,, -- - -

-,-e e..,r----,,-amm-----

-n-->s-. .~,,-,-e- +-v - a.-., ,. . , , - - --. - -, ,. ,- -

Projects 207TD3501 4

,. PROBLEM: To estimate End of Life (EOL) Fluence for Unit I and Unit 2 to support Pressurized Thermal Shock (PTS) study for a NRC letter by January 26, 1986.

Assume fluence relates directly to peak burnup of the assembly on the flat closest to the critical weld. Using data gathered from the analysis of a surveillance capsule from Unit i EOC. 3, develop a correlation of burnup to neutron fluence. Relate this to Unit 2 and predict EOL fluences for both Units. The assembly to be used has the location designation Y-10. For the correlation, the peak burnups for this assembly are gathered from from EOC INCA option 10 for each cycle.

The EOC burnups for assembly Y-10 are given for both Units in Tables I and 2.

This calculation is done by assuming that we continue with a high leakage scheme of fuel management. If we go to low leakage, 2ti-month cycles, this fluence calculation will be' reduced. The assumption that the fluence varies only with the peak burnup of Y-10 and not the surroundings may be non-conservative, but it should be compensated for by the conservative approaches taken.

4 e

T 4

, -.,-.m ,-------.-,-,-+n. .,, w w -- ,--,-,,.--,,-,,,e , , , ,-,,-- 4 -- -- , - - ~ , -,~, ,-,n

Projects /207TD8501 9

s.

TABLEl Unit 1 Assembly Y-10 Cycle Peak Assembly Burnup (MWD /T)

Effective Fall Axial Location (f t) Power Years 1 14,469 3.54 1.4275 2 9,103 3.31 s- 0.6964 3 9,403 3.31 0.8131 4 11,679 3.08 1.0045 5 13,153 3.31 1,1022' 6 14,131 2.63 1.115 7 14,135 2.36 1.1196 -

, TABLE 2 Unit 2 Assembly Y-10 .

Cycle Effective Full Peak Assembly Burnup (MWD /T) Axial Location (f t) Power Years-1 14,145 3.31 1.3364 2 9,779 3.08 0.82623

-3 10,876 3.31 0.95102 4 15,657 3.31 1.33947 5 12,479 3.31 1.1209 6 13,595 3.31 1.12903

Projects 207TD8501 ,

J

~~

To Es*imate Unit i EOL Fluence ,

From the surveillance . capsule removed after cycle 3, the fluence at the vessel wall was calculated to be:

4.34 x 10 13 neutron /cm 2 (Reference 1)

(Energy)1 Mev)

There are two ways to calculate EOL' fluence. Develop a fluence to burnup relationship with assembly Y-10 or develop a fluence to EFPY relationship.

We will do both and take the one that is more conservative.

" I "

A. 4.34 x 10 2

= 1.317 x 10 2 Per an an 32,973 W D T

" I "

B. 4.34 x 10 = 1.478 x 10 2 per EFPY i ,2 2,937 EFPY ,

Af ter 7 cycles fluences would be:

= 1.133 x 10I '

A. 86,073 T

x 1.317 x 10 2 Per T 2 B. 7.2364 EFPY x 1.478 x 10 2 Per EFPY = 1.07 x 10 2 an an Thus the first method is conservative.

To project an end of life burnup, a capacity factor of .80 is assumed for the life of the plant. Thus with a 40-year license, the total EFPYs are

(.8)40 = 32 EFPY.

Through cycle 7, there had been 7.2364 EFPY. To find no T Per EFPY:

36,073 T T

= 11,894 g 4

7.2364 EFPY l

To be conservative, cycles 6 and 7 are closer to equilibrium cycles and have a  ;

maximum of:

WD 12,673 EFPY 1

Projects 207TD3501 huD

  • T Therefore, I will' use 13,000 to be conservative for future cycles.

EFW

' calculating remaining EFPY (32-7.2364) = 24.7636 EFPY 1

Thus for cycles 8 through EOL, the peak burnup for assembly Y-10 will be:

AMO (13,000 EF h ) x (24.7636 EFP() = 321,927 ^*T The total burnup for all' cycles would be:

321,927 + 86,073

.= 408,000 .g.

]

From Equation 1, the total EOL fluence would be:

(1.317 x 10I " "

) (408,000 I9 2 Per T hD)=5.373x10

} E>l Mev 1

b J

t i

4 i

! e i

f

. , , - . . . . -- - , , - , , , n-,, , - . - ,,,- . - . . , , . - - . . . ~ , - - . , - , . - , , - -

..-,----~,,..-,...,.-c.,-, , _ . , , , . - - - , , _ , -_,...--_~,,-n-,.

Projects 207TD8501

. To estimate EOL fluence for Unit 2:

Because of the similar core loading of Unit 2 as compared to Unit 1, we can assume the same fluence to burnup relationship:

1.317 x 10 I4 neutron /cm2 per ^

T Through cycle 6, Unit 2 has a burnup of:

Am' 76,531 nd 6.753 EFPY (From Table 2)

T For cycle 7 to EOL, there is:

(32-6.753) = 25.247 EFPY From Equation 2, the peak assembly burnup will be:

WD (25,247 EFPY) x (13,000 ) + 76,531 ' D EFPY T

= 404,742 Thus, EOL fluence would be:

n

~

2

) = 5.33 x 10 I l (404,742 D ) (l.317 x 10 A$D 2 T "

l E>l Mev.

. To ensure these values are conservative, here is a relationship from CE.

Fluence Accumulation Rate is

J 8 "

j 1.48 x 10 2 Per EFPY (Reference 2) on i

i This relation would give an EOL fluence for both Units of:

4.74 x 10 I 2

an j Therefore, this approach is conservative.

i a

.- . --,, - - , _ -_ , - . . _ . _ _ - - , , . . , , . . - , . _ . . - - . _ , - _ _ _ , . . . . _ . . . _.m. --. .,_ -._m.-__._,_,_.

Project 207TD3501 g REFERENCES

1. Calvert Cliffs Unit No.1 Nuclear Power Plant Reactor Pressure Vessel Surveillance Program: Capsule 263. Battelle, Columbus Laboratories,

, December 1980.

2. Evaluation of Pressurized Thermal Siiock Effects Due to Small Break LOCAs with Loss of Feedwater for the Calvert Cliffs I and 2 Reactor Vessels.

Combustion Engineering, Inc., December 1931, GEN-139, Appendix B.

3. Fluence Calculations for PTS Fracture Mechanics Analyses. M. E. Bowman, WN 83-102, October 1933.

1 I

l 1

l a

l i

1

- ~ , - - , - - - , , - , , - - -. ,, , ,, , .., , - , , _ - - - - - . , , - , - - . , - - r- ,--.

Retrieved from "https://kanterella.com/w/index.php?title=ML20212P040&oldid=3097017"