ML13322B172

Rev 1 to SONGS 1 Reactor Vessel Adjusted Ref Temp for 16 & 24 Efpy

ML13322B172
Person / Time
Site:	San Onofre
Issue date:	03/29/1990
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13316A548	List: ML13316A547 ML13322B171 ML13322B172 ML20043G671
References
DC-3115, DC-3115-R01, DC-3115-R1, NUDOCS 9006200547
Download: ML13322B172 (19)

Text

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SIGNATURE Independent Review Engineer Date__

SIGNATURE ORIGINAL ISSUE NAME DATE SIGNATURE Group Leader PsCi 2

J24tAf Discipline Sup. Engineer Lo Ct C\\

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bt Professional Engineer (if required)

RECORD OF REVISIONS NO.

REASON FOR REVISION DATE RESP. ENGR.

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PROFESSIONAL ENGINEER'S SEAL C

26-12t REV 10/84

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D RPAGE O F DESIGN INPUT SHEET Design Requirements PA3115E Li Design Input Change I

1 SUJECT el Adjs e4 PROJECT Tenage e r* Ar - Fr lb Jn 2q r-EFPY.-

Sot4 S

i QUALITY CLASS SEISMIC CLASS SPECIFICATION REFERENCE SR I

ASME Code sec Design Input e

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RESPONSIBLE ENGINEER DATE INorPENDET Ew ENGINEER DAT ROU LEAD DATE SCE Z-a11 RV s/l

SHEET 0F 17 S3H EETS ENGINEERING DEPARTMESH CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115

SUBJECT:

CALCULATION NO.

REVISION P. Brashear 3/10/90 2

JO. No.

MADEBY DATE CHK.9 8

E TABLE OF CONTENTS Page

1.

PURPOSE 3

2. METHODOLOGY 3

3.

RESULTS 4

4.

REFERENCES 5

5. ASSUMPTIONS 6

6. NOMENCLATURE 7

7.

CALCULATIONS 8

7.1 Limiting Material 8

7.2 Chemistry Factor (CF) 8 7.3 Fluence 11 7.4 Nil-Ductility-Transition-Temperature Shift 13 7.5 Adjusted Reference Temperature Margin 13 7.6 Adjusted Reference Temperature 14

8.

CONCLUSIONS 14 DWG, NO.

SHEET OF 17 SHEETS ENGINEERING DEPARTME HE CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted SUnwT Reference Temperature For 16 & 24 EFPY DESIGN DC 3115 ATE CALCU1LATION NO. _________EVISICN N.0.mo.

MADE BY P.

Brashear 3/10/90 eHK.A

1.

PURPOSE The current RCS Pressure-Temperature (P-T) operating limits (heatup and cooldown curves) are based on reactor vessel adjusted reference temperatures (adjusted RTNDT) determined by Westinghouse and previously considered valid for 16 EFPY.

Regulatay Guide 1.99 Revision 2 (Reference 1) introduces changes which significantly affect the methods used to predict irradiation induced shifts in adjusted RTNDT values. Under the new regulation revision, the predicted adjusted RTNDT values used in determining the current P-T limits may not be conservative; and therefore the heatup and cooldown limits.(Technical Specification 3.1.3) may not be valid for the entire operating period considered.

In accordance with NRC Generic Letter 88-11 (Reference 2), this design calculation determines SONGS1 adjusted RTNDT values per Reference 1, and evaluates the validity of the existing P-T limits.

In addition, Reg. Guide 1.99 Rev. 2 based adjusted RTNDT values will be determined for 24 EFPY (end-of-life conditions) and compared with values predicted by Westinghouse.

2. METHODOLOGY The adjusted RTNDT is determined by adding the expected shift in Reference Temperature (ARTNOT) due to neutron irradiation, to the initial unirradiated Reference Temperature (initial RTNDT) for all reactor vessel beltline materials. These materials have previously been identified and their initial RTNDT values are available (Reference 3).

The Reference Temperature shifts are determined per the guidelines of Reference 1, Section 2.1, using SONGS 1 surveillance data, and evaluated at the operational periods (fluences) of interest (16 and 24 EFPY) for the vessel wall 1/4 thickness and 3/4 thickness locations.

In accordance with Reference 1, a margin term M is determined and included in calculating adjusted RTNDT values for conservatism.

The highest adjusted RTNDT value calculated for all beltline materials determines the limiting material (or materials, since a different plate or weld can be limiting at different vessel wall thicknesses).

These adjusted RTNDT values for the limiting material(s) are then compared with the Westinghouse determined values (Reference 4) from which the existing P-T curves are based.

DWG. NO.

ENGINEERING DEPARTME SHEET OF SHEETS CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted EFY ESIGN D315EVSO SUBJECTReference Temperature For 16 & 24 EFPY 1,0CI".v oDC 3115 REVISION J.O. NO.

MADE BY P.

Brashear DATE 3/10/90 CHK. 8 ATE

3. RESULTS The adjusted RTNDTs for the reactor vessel beltline limiting materials at the vessel wall 1/4 and 3/4 thickness locations are shown below. Adjusted RTNDT values for the limiting materials at operating periods of 16 and 24 EFPY using Reg.

Guide 1.99 Rev. 2 methods are shown below. Values predicted using Westinghouse methods (References 9 and 11) are provided for compariton.

SONGS1 Adlusted RTNDT (OF) 16 EFPY 24 EFPY R.G. 1.99 R.G. 1.99 Rev. 2 W

Rev. 2 W

1/4 T Location (Plate W7601-9) 217 235 (Plate W7601-1) 186 194 3/4 T Location (Plate W7601-5) 163 172 (Plate W7601-1) 159 168 OWG. NO.

SHEET O F 17 SHEETS ENGINEERING DEPARTMEI CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY CoUATIONo.

DC 11I5REVSsoN

SUBJECT:

J.O. NO.

MADEBY P.

Brashear DATE 3/10/90 CHK.

/

TE

4. REFERENCES

1. Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.

2. NRC Generic Letter 88-11, "Position on Radiation Embrittlement of Reactor Vessel Materials and It's Impact on Plant Operations", July 12, 1988.

3. K. P. Baskin (SCE) to H. R. Denton (NRC) Docket #50 206, "Heatup and Cooldown Curves SONGS Unit 1", April 18, 1980.

4.

K. P. Baskin (SCE) to H. R. Denton (NRC) Docket #50 206, "Amendment Application No. 118 SONGS Unit 1",

May 17, 1984.

5. ASTM Standard E208-87a, "Standard Test Method for Conducting Drop-Weight Test to Determine Nil Ductility Transition Temperature of Ferritic Steels", Volume 03.01, 1988.

6. M. 0. Medford (SCE) to G. E. Lear (NRC), "Pressurized Thermal Shock SONGS 1", January 23, 1986.

7. Southwest Research Institute, "Analysis of First Surveillance Material Capsule From San Onofre Unit 1",

July, 1971

8. Southwest Research Institute, "SONGS1 Analysis of Second Surveillance Material Capsule From San Onofre Unit 1",

July, 1972

9. Westinghouse Electric Corporation, "Analysis of Capsule F From The Southern California Edison Company, San Onofre Reactor Vessel Surveillance Program",

May, 1979

10.

Westinghouse Report, San Onofre Unit 1 Reactor Vessel Fluence Calculation, PTS Evaluation and Flux Reduction Factor Curves, March, 1990

11.

K. P. Baskin to USNRC, "Docket No. 50-206 Pressurized Thermal Shock to Reactor Pressure Vessels SONGS Unit 1", January 25, 1982

12.

Westinghouse Report, "Summary Report on Reactor Vessel Integrity for Westinghouse Operating Plants",

WCAP-10019, December 1981

13.

S. Anderson to P. F. Brashear, Westinghouse Letter #FSE-REA 90/941, "SCE Capsule Fluence Comparisons", April 6, 1990 DWG. NO.

SCE 00 397-B REV 0/4 (CW)

SHEET OF 17 SHEETS ENGINEERING DEPARTME*

CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted e

SSUBJEReference Temperature For 16 & 24 EFPY sIATOGN

0. DC 3115 REVISION P.

Brashear DATE 3/10/90 cuK.

4 v W

O.NO.

MADEB

-C_________

ATK

5.

ASSUMPTIONS

1. Maximum expected vessel fast fluxes and fluences have been determined by Westinghouse (References 6, 10) using SONGS 1 surveillance capsule data. These values are conservative.

2. Initial RTNDs and material chemistry are taken from Reference 3. Where no chemistry analysis is available, conservative estimates are used (reference 6).

3. Techniques for determining RTNDT shifts from plant surveillance data per Section 2 of Reference 1 are conservative; i.e.,

RTNDT shifts for materials of different chemistry can be determined by correcting surveillance data using the ratio of chemistry factors.

4. Fast flux is attenuated through the vessel wall per Reference 1.

5. Maximum possible vessel initial crack depths are 1/4 thickness deep and occur at the vessel wall OD or ID.

6. Vessel EOL is 24 EFPY.

7. a, is 50F for base metal as initial RT values were measured in accordance with ASTM standard E208-87a.

8. Margin M is 59 0F for all welds per 10CFR50.61 (b.2.i).

Mean generic values were used for these weld's initial RTNDT and a..is unavailable; therefore, the recommended margin for the PTS rule is used and considered conservative.

9. SONGS1 reactor vessel wall thickness is 9.91 inches.

This is the minimum plate thickness in the beltline region.

10.

Nickel content for the vessel shell plate material is 0.20%. The nickel content was not directly measured, but is known to be less than 0.20 weight percent because this was the specification limit for the steel (SA302B) used.

11.

The weld copper and nickel contents are not available, but are conservatively estimated as 0.27% and 0.20%

(References 11, 12).

DWG.NO.

SCE 00 397-8 REV i0/A (cW)

ENGINEERING DEPARTME SHEET 7

- F 17 EETS CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted so1arTReference Temperature For 16 & 24 EFPY OEIGN NOys.DC 3115 REVISION J. 0. NMADE BY P.

Brashear DATE 3/10/90 CHK. 8

-6_D ATE

6.

NOMENCLATURE ART Reactor vessel limiting material adjusted reference temperature evaluated at vessel wall 1/4 thickness and/or 3/4 thickness location (OF).

CF Chemistry factor per Reference 1.

ff Fluence factor per Reference 1.

f, Fluence at reactor vessel ID surface (n/cm 2

f1/4T -

Fluence at reactor vessel 1/4 T flaw location (n/cm f3/4T -

Fluence at reactor vessel 3/4 T flaw location (n/cm2).

M Margin to be used in determining ART to cover uncertainties per Reference 1 (OF).

RTNDT -

Reactor vessel material nil-ductility-transition reference temperature (or ART), (OF).

ARTXDT-Shift in nil-ductility-transition reference temperature due to vessel irradiation (OF).

ai Standard deviation for the initial RTNDT, based on measured or generic data (oF).

aA

- Standard deviation for ARTNDT, (14 0F for welds, 8.5 0F for base metal, Reference 1).

T

- Reactor vessel wall thickness (inches).

x Reactor vessel wall radial position, measured from wall ID (inches).

DWGNO.

ser or re-n mru

ENGINEERING DEPARTMES CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115

SUBJECT:

CALCULATION NO.

REVISION JO.NO.

MADEBY P. Brashear DATE 3/10/90 CHK. BY T E 7.. CALCULATIONS 7.1 Materials The limiting reactor coolant pressure boundary material for irradiation embrittlement and fracture toughness considerations was previously determined to be intermediate shell plate W7601-9 for the 1/4 T location, and lower shell plate W7601-5 at the 3/4 T location, using the methodology presented in Reference 3. Due to changes in radiation damage correlations, Reference 1 must now be used to determine the ARTs for the vessel beltline weld, heat affected zone (HAZ),

and plate metals. This will be done for fluences equivalent to 16 and 24 EFPY (EOL: 30 years @ 80% capacity).

The largest resulting ART at the 1/4 T and 3/4 T locations will dictate the vessel limiting material.

The relative locations of the beltline materials considered are shown in Figure 1. Plate and weld reference numbers and material properties are listed in Tables 2 and 3. The methods used to determine the intermediate step parameters (summarized in Tables 2 & 3) are shown below.

7.2 Chemistry Factor (CF)

The Chemistry Factor for the various plates and weld metal is determined from Section C.2.1 of Reference 1.

Reference 1 states, "calculate the chemistry factor, CF, for the best fit by multiplying each adjusted ARTNDT by its corresponding fluence factor, summing the products, and dividing by the sum of the squares of the fluence factors". This can be represented by the following equation:

CF =

Z(ARTIT*ff)

/ Z(ff 2) and is the least squares fit of the surveillance data to the NRC correlation used in Section 7.4 of this calculation.

In addition, Reference 1 states if "the copper or nickel content of the surveillance weld (plate) differs from that of the vessel weld (plate), i.e., differs from the average of the weld wire heat number associated with the vessel weld and the surveillance weld, the measured values of ARTNDT should be adjusted by multiplying them by the ratio of the chemistry factor (Reference 1, Table 2) for the vessel weld (plate) to that for the surveillance weld (plate).

Copper and nickel content for the beltline materials are provided in Table 2.

DWG. NO.

SCE DO 397-B REV 10s4 (CW)

ENGINEERING DEPARTME@

CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted

,,,,,TReference Temperature For 16 & 24 EFPY DESION DC 3115 SJ r NrMA BAL UL TION N REV ION J..

NO.

MADE Brashear DATE 3/10/90 CHK. a

/

WATE The surveillance capsule results needed for computation of the chemistry factors are summarized in Table 1 below. Shifts in RTNDT are those values measured and reported in the surveillance capsule reports (References 7-9).

Fast fluences provided result from a reanalysis (Reference 13) using the surveillance reports activation data and updated transport codes and a more detailed capsule geometric model.

Table 1 Fluence ARTNT (OF)

Capsule n/cm ff W7601-1 W7601-8 W7601-9 Weld HAZ A

1.8E19 1.161 100 80 80 D

3.4E19 1.320 140 110 130 F

4.9E19 1.398 120 145 115 where ff is the fluence factor as defined in Reference 1:

ff = fluence(0.28 -

0.10 log fluence)

Per Reference 1, at least 2 data points are needed to use in determining CF.

For the plate material, plates W7601-8 and W7601-9 both meet this requirement. Furthermore, since these plates have the same copper and nickel content (Table 1),

similar residual elements content (Reference 8), similar initial RTNDTs, and the same heat treatment (microstructure), it is valid to group the 4 data points together and treat plates W7601-8 and W7601-9 as the same material (plate W7601-1 has slightly different copper content, and is therefore not included).

The weld and HAZ metal have 2 valid surveillance data points, which are used in determining CF.

Using the above equation, chemistry factors are determined for the beltline materials:

W7601-1 CF = (88/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612

+ 1.320

+ 1.398 +

1.3202 CF = 84.7 W7601-8 CF = (100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612 + 1.3202 + 1.3982 +

1.320 )

CF = 88.5 DWG. NO.

SHEET 10 OF 17 SHEETS ENGINEERING DEPARTMEf CALCULATION SHYET SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115 JO1. N.__________

AEBY_____________DT CALCULATION NO. _

______REVISION P.

Brashear 3/10/90 J.

.o0. No0.

MADE BY-DATE CHK. BW r

• DATE W7601-9 CF = (100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.161

+ 1.320

+ 1.398 +

1.3202 CF = 88.5 W7601-3 CF = (80/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.161

+ 1.320 +

1.398

+

1.3202 CF = 77.0 W7601-6 CF = (84/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612 + 1.320

+ 1.398

+

1.320 CF = 80.8 W7601-7 CF = (80/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612

+ 1.320 +'1.398

+

1.320)

CF = 77.0 W7601-2 CF =

(88/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612

+ 1.320

+ 1.398 2+

1.320)

CF = 84.7 W7601-4 CF =

(75/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612

+ 1.3202 + 1.398 2+

1.3202 CF = 72.1 W7601-5 CF = (75/92)*(100*1.161 + 110*1.320 + 130*1.320 +

120*1.398)/(1.1612 + 1.320

+ 1.398

+

1.320 )

CF = 72.1 Chemistry factors for the welds are determined from the surveillance weld data.

Since weld chemistry is assumed the same for all welds, no chemistry correction is necessary:

DWG.NO.

SCEOD0397-B REVi6/84 (CW)

SHEET OP 7

SHEETS ENGINEERING DEPARTMES CALCULATION H ET SONGS 1 Reactor Vessel Adjusted SSU JECReference Temperature For 16 & 24 EFPY DESIGN DC 3115 iiRICT:

CALCUrLATION NO.

REVISION P.

Brashear 3/10/90 W

.O. NO._MADE BY DATE CHK.

B '

L

-)

DATE Welds CF = (80*1.161

+ 145*1.398)/(1.161

+ 1.3982)

CF = 89.5 Chemistry factors for HAZ is determined from the surveillance HAZ data. Since the surveillance HAZ copper and nickel content (from plates W7601-8 and W7601-9) is the highest of any vessel HAZ material, the measured surveillance data does not need to be corrected for chemistry:

HAZ CF = (80*1.161 + 115*1.398)/(1.1612 + 1.398 CF = 76.8 These chemistry factors are listed in Table 2 and 3.

7.3 Fluence Fluences for the vessel beltline materials are determined below for the vessel wall I.D. surface, 1/4 T, and 3/4 T locations.

Surface Fluence (f)_

I.D. surface fluences are obtained from References 10 and 11, and are considered conservative. Fast fluxes used to determine fluences for a given plate or weld were evaluated at the position of highest azimuthal and axial flux peaking.

The vessel peak fluence locations occur in intermediate shell plates (W7601-1, W7601-8, and W7601-9) and longitudinal weld 7-860A. The 16 and 24 EFPY maximum fluences for these 22 materials are given in Reference 10 as 4.73E19 n/cm and 6.84E19 n/cm.

The maximum fluences for the remaining beltline materials are obtained from Reference 11.

Subsequent analysis (Reference 10) has shown the values determined in Reference 6 using Reference 11 overpredict the vessel fast fluxes and fluences. However, since Reference 10 did not explicitly determine the fluence for the remaining plates and welds, the values determined in Reference 6 will be used for these materials. This is conservative because the earlier analysis did not account for low leakage fuel patterns used since Cycle 7. This provides additional margin to the calculation of ARTNDT.

From Reference 6, these surface fast fluxes are:

Plates W7601-3, W7601-6, W7601-7 = 2.21E18 n/cm2/EFPY Plates W7601-2, W7601-4, W7601-5 = 1.11E18 n/cmz/EFPY DWG. NO.

SCE 00 397-8 REV sa (CW)

SHEET

17. O 17 SHEETS ENGINEERING DEPARTMEAT CALCULATION SH T

SONGS 1 Reactor Vessel Adjusted SUDETReference Temperature For 16 & 24 EFPY DAE.I NODC 3115 SIO_

0

.0.

NO.

MADEBY P.

Brashear DATE 3/10/90 DCHK.

B

'ATE Longitudinal Weld 7-860B = 1.20E18 n/ M2/EFPY Longitudinal Weld 7-860C = 0.695E18 n/CM 2/EFPY Longitudinal Weld 6-860A = 0.720E18 n/cm 2/EFPY Longitudinal Weld 6-860B = 0.417E18 n/CM 2/EFPY Longitudinal Weld 6-860C = 1.80E18 n/cm /EFPY Longitudinal Weld 8-860A = 0.36E18 n/cm2/EFPY Longitudinal Weld 8-860B = 0.208E18 n/cm2/EFPY Longitudinal Weld 8-860C = 0.90E18 n/cm 2/EFPY Circumferential Weld 1-860 =.11E.8 n/CM 2/EFPY Circumferential Weld 2-860 = 2.21E18 n/ m2/EFPY These fluxes are multiplied by 16 and 24 EFPY to obtain the fluences listed in Tables 2 and 3, respectively.

Vessel wall 1/4 T Fluence ( fl/4T)

Vessel wall 1/4T fluences are obtained by attenuating the surface fluences per Reference 1 (x as defined in the nomenclature):

fx = f,( -o.24X)

For example, the 1/4 T fluence (16 EFPY) for shell plate W7601 1=

(4.773E19) (e0

/

2 4 c

9 1 E) 1/4T n

2.61E19 1/4 T fluences at 16 and 24 EFPY for the remaining beltline materials are determine in the same manner and have been listed in Tables 2 and 3.

Vessel wall 3/4 T Fluence (f3/4T)

Vessel wall 3/4T fluences are obtained by attenuating the surface fluences per Reference 1:

fx =

f (-0.24x For example, the 3/4 T fluence (16 EFPY) for shell plate W7601-1 is:

f3/4T = (4.73E19) (e-0.

2 4(9.91 3/ 4 )

f3/4T = 0.795E19 3/4 T fluences at 16 and 24 EFPY for the remaining beltline materials are determine in the same manner and have been listed in Tables 2 and 3.

SCE s

e 3w7-a REV 3//4 (Cw)

Fl e

c (O.

SHEET 13 OF 1'7 SHEETS ENGINEERING DEPARTME CALCULATION SPET SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115 11Fl.IF T

C.i fll itTION1 NoDC 3 1 REVISION J.O. NO.-

MADEBY P.

Brashear DATE 3/10/90 CHK. 8 DATE 7.4 Nil-Ductility-Transition Temperature Shifts (ART,)}.

The shift in RTNDT is determined from Reference 1:

ARTNDT CF

• f(0.2 8 -

0.1 log f) where f is the fluence (x1019 ) evaluated at 1/4 T or 3/4 T, and at either 16 EFPY (Table 2) or 24 EFPY (Table 3).

For example, ARTNDT at 16 EFPY at 1/4 T for plate W7601-1 is:

ARTNDT

= 84.7(2.61 (0.28 - 0.1 log(2.61))

ARTNDT = 106.5 OF The remaining transition temperature shifts are determined in the same manner and have been listed in Tables 2 and 3.

7.5 ART Margin (M)

"Margin", M, is the quantity (OF) that must be added to obtain conservative, upper-bound values of adjusted reference temperature (ART) for the calculations necessary to meet the requirements of Appendix G to 10CFR50.

M = 2 (f

+

af 2) a1 is the standard deviation for the initial RTNDT.

The initial RTNDTs for the beltline materials were measured values established in accordance with Reference 5.

These values (listed in Tables 2 and 3) were determined through break/no-break specimen fracture tests conducted at 50 ft-lbs at 10 0 F increments.

The initial RTNDT is the highest tested temperature at which the specimen breaks for given loading conditions.

ai is chosen as half of the test temperature increment, 50F.

al for the welds is unknown because mean generic data was used in establishing the welds initial RTND.

UA is the standard deviation for the shift in RTNET.

Per Reference 1, based on generic data a

= 28 0F for welds and 170F for plates; however, half these values can be used when surveillance data is used in determining ARTNDT.

Therefore, for base metal, M = 2 ((5) + (17/2) )

M = 19.70F DWG.

NO.

SSHEET OF I-SHEETS ENGINEERING DEPARTME 7

E CALCULATION SHEET SONGS 1 Reactor Vessel Adjusted

)

,u,,cReference Temperature For 16 & 24 EFPY DESIGN DC 3115 REVISION

.o. NO.

MADE BY P. Brashear DATE 3/10/90 CHK. B DATE For welds, since there was no direct measurements for the vessel welds initial RTNDT and al for the generic data base is unknown, per 10CFR50.61(b)(2)(i), a conservative margin recommended which is consistant with the generic data base is:

M = 590 F 7.6 Adjusted Reference Temperatures (ARTs)

The ART is the initial NDT Reference Temperature adjusted for material embrittlement (ARTNDT) for the exposure period being considered, and includes a margin term:

ART = initial RTNDT +

6RTNDT + M For shell plate W7601-1 at the 1/4 T location and 16 EFPY, ART = 60 + 106.5 + 19.7 OF ART = 186.2 0 F ARTs for the remaining beltline materials at 1/4 T and 3/4 T locations and for 16 and 24 EPPY exposure conditions have been determined in a similar manner and are listed in Tables 2 and 3.

8. CONCLUSIONS SONGS1 existing Technical Specification 3.1.3 (Heatup and Cooldown Curves) is based on ARTs of 217 0 F and 1630 F at the 1/4 T and 3/4 T location, respectively. Reference 1 was used to determine ARTs for the limiting beltline materials under the new regulatory guidelines. The maximum ARTs for the beltline materials at 16 EFPY were found to occur for intermediate shell plate W7601-1, and are 186.2 0 F at 1/4 T, and 158.9 0F at 3/4 T.

These values are less than those used to develop the existing P T limits (heatup and cooldown curves); therefore, it is concluded the existing curves continue to provide sufficient margin to account for neutron radiation damage through 16 EFPY of operation.

In addition, ARTs were determined for end-of-life conditions (24 EFPY).

At 1/4 T and 24 EFPY, the limiting material is intermediate shell plate W7601-9 with an ART of 193.60 F. At 3/4 T and 24 EFPY, the limiting material is intermediate shell plate W7601-1 with an ART of 167.7 0F.

DWG. NO.

SCEOD0397-B REVie0/a4 cw)

SHEET OF 17 SHEETS ENGINEERING DEPARTMEN CALCULATION SH T SONGS 1 Reactor Vessel Adjusted sUBJCT.Reference Temperature For 16 & 24 EFPY SN o DC 3115 s

J.0. No0.

MADEBY P. Brashear DATE 3/10/90 c....

DAoE 2700 601-6 6-860A 6-860M 1800

0. 0 W7601-7 6-860C 860 2700 7-8604 zT W7601-9 W7601-8 7-860B 7-860C

-CIO 0

W601-1 2700 W601-4 1

8-8608 1-860 W7601-2 W601-5 900 Figure

1.

Identification and Location of Beltline Region Material of the San Onofre Unit 1 Reactor Vessel DWG. NO.

SCE 00 397-8 REV 10/84 (CW)

ENGINEERING DEPARTME CALCULATIONS T

SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115 SUBJECT CALCULATION NO.

REVISION J.. NO.

MADE BY PD Brashear DATE 3/10/90 CHK. 8 A

~

T A T E Table 2 Adjusted Reference Temperature (ART) for SONGS 1 Reactor Vessel Beltline Materials at 16 EFPY (b)

(a)

Initial (c)

ID (d) 1/4 T 1/4 T 1/4 T 3/4 T 3/4 T 3/4 T Cu Ni RTndt M

Fluence Fluence &STndt ART Fluence ARTndt ART Material

(%)

(%)

(F)

(F)

( tol n/ca CF (lo" n/ca')

(F)

(F)

(1o" n/cm')

(F)

(F)

Inter.

Shell W7601-1 0.17 0.2 60 19.7 4.73 84.7 2.610 106.5 186.2 0.795 79.2 158.9 Inter. Shell W7601-8 0.18 0.2 40 19.7 4.73 88.5 2.610 111.2 170.9 0.795 82.8 142.5 Inter. Shell W7601-9 0.18 0.2 55 19.7 4.73 88.5 2.610 111.2 185.9 0.795 82.8 157.5 Upper Shell W7601-3 0.15 0.2 8

19.7 3.54 77.0 1.953 91.1 118.8 0.595 65.8 93.5 Upper Shell W7601-6 0.16 0.2 24 19.7 3.54 80.8 1.953 95.6 139.3 0.595 69.0 112.7 Upper Shell W7601-7 0.15 0.2 12 19.7 3.54 77.0 1.953 91.1 122.8 0.595 65.8 97.5 Lower Shell W7601-2 0.17 0.2 34 19.7 1.78 84.7 0.982 84.3 138.0 0.299 56.7 110.4 Lower Shell W7601-4 0.14 0.2 51 19.7 1.78 72.1 0.982 71.7 142.4 0.299 48.3 119.0 Lower Shell W7601-5 0.14 0.2 82 19.7 1.78 72.1 0.982 71.7 173.4 0.299 4.8.3 150.0 Long. Weld 7-860A 0.27(a) 0.2

-56 28.4 4.80 89.5 2.649 112.8 85.2 0.806 84.1 56.5 Long. Weld 7-860B 0.27(a) 0.2

-56 28.4 1.92 89.5 1.059 90.9 63.3 0.323 61.7 34.1 Long. Weld 7-860C 0.27(a) 0.2

-56 28.4 1.11 89.5 0.612 77.2 49.6 0.186 49.5 21.9 Long. Weld 6-860A 0.27(a) 0.2

-56 28.4 1.15 89.5 0.635 78.1 50.5 0.193 50.2 22.6 Long. Weld 6-860B 0.27(a) 0.2

-56 28.4 0.67 89.5 0.370 64.9 37.3 0.113 39.5 11.9 Long. Weld 6-860C 0.27(a) 0.2

-56 28.4 2.88 89.5 1.589 100.9 73.3 0.484 71.4 43.8 Long. Weld 8-860A 0.27(a) 0.2

-56 28.4 0.58 89.5 0.320 61.5 33.9 0.097 36.8 9.2 Long. Weld 8-860B 0.27(a) 0.2

-56 28.4 0.33 89.5 0.182 49.0 21.4 0.055 27.7 0.1 Long. Weld B-860C 0.27(a) 0.2

-56 28.4 1.44 89.5 0.795 83.7 56.1 0.242 55.1 27.5 Circum. Weld 1-860 0.27(a) 0.2

-56 28.4 1.78 89.5 0.982 89.0 61.4 0.299 59.9 32.3 Circum.

Weld 2-860 0.27(a) 0.2

-56 28.4 3.54 89.5 1.953 105.9 78.3 0.595 76.5 48.9 HAZ 0.18 0.2 0

19.7 4.73 76.8 2.610 96.5 116.2 0.795 71.8 91.5 (a) Conservative estimate - no analysis available.

(b) Initial eference Temperature measured cr generic mean value per 10CFR 50.61(b)(2)(i).

(c) FMargin to be added to cover uncertainties per Regulatory Guide 1.99 Rev. 2. Section 2.1 for plates, 10CFR30.51(b)(2)(i) generic mean value margin for welds.

(d) Reference 6.

(e) Chemistry Factor determined per Regulatory Guide 1.99 Rev. 2. Section 2.1 Using SO;GS 1 surveillance data.

DWG. NO.

SCE OD 397-B REV sels4 (Ctwl

SHEET 17OF 7 SHEETS ENGINEERING DEPARTMET CALCULATION SH T

SONGS 1 Reactor Vessel Adjusted Reference Temperature For 16 & 24 EFPY DESIGN DC 3115 J.O. NO.

MADE BY P. Brashear DATE 3/10/90 CK. B T E Table 3 Adjusted Reference Temperature (ART) for SONGS 1 Reactor Vessel Beltline Materials at 24 EFPY (b)

(a)

Initial (C)

ID (d) 1/4 T 1/4 T 1/4 T 3/4 T 3/4 T 3/4 T Cu Ni RTndt M

Fluence Fluence ARTndt ART Fluence ARTndt ART Material

(%)

(%)

(F)

(F)

(10" n/enz CF (10" n/cm 1 )

(F)

(F)

(10 n/ca)

(F)

(F)

Inter.

Shell W7601-1 0.17 0.2 60 19.7 6.84 84.7 3.774 113.8 193.5 1.149 88.0 167.7 Inter.

Shell W7601-8 0.18 0.2 40 19.7 6.84 88.5 3.774 118.9 178.6 1.149 91.9 151.6 Inter. Shell W7601-9 0.18 0.2 55 19.7 6.84 88.5 3.774 118.9 193.6 1.149 91.9 166.6 Upper Shell W7601-3 0.15 0.2 8

19.7 5.30 77.0 2.925 98.9 126.6 0.890 74.5 102.2 Upper Shell W7601-6 0.16 0.2 24 19.7 5.30 80.8 2.925 103.8 147.5 0.890 78.2 121.9 Upper Shell W7601-7 0.15 0.2 12 19.7 5.30 77.0 2.925 98.9 130.6 0.890 74.5 106.2 Lover Shell W7601-2 0.17 0.2 34 19.7 2.66 84.7 1.468 93.7 147.4 0.447 65.7 119.4 Lower Shell W7601-4 0.14 0.2 51 19.7 2.66 72.1 1.468 79.8 150.5 0.447 55.9 126.6 Lower Shell W7601-5 0.14 0.2 82 19.7 2.66 72.1 1.468 79.8 181.5 0.447 55.9 157.6 Long. Weld 7-860A 0.27(a) 0.2

-56 28.4 6.84 89.5 3.774 120.2 92.6 1.149 93.0 65.4 Long. Weld 7-860B 0. 2 7 (a) 0.2

-56 28.4 2.88 89.5 1.589 100.9 73.3 0.484 71.4 43.8 Long. Weld 7-860C 0.27 0.2

-56 28.4 1.67 89.5 0.922 87.4 59.8 0.281 58.5 30.9 Long. Weld 6-860A 0. 2 7 (a) 0.2

-56 28.4 1.73 89.5 0.955 88.3 60.7 0.291 59.3 31.7 Long. Weld 6-860B 0.27 0.2

-56 28.4 1.00 89.5 0.552 74.6 47.0 0.168 47.3 19.7 Long. Weld 6-860C 0. 2 7 (a) 0.2

-56 28.4 4.32 89.5 2.384 110.5 82.9 0.726 81.5 53.9 Long. Weld 8-860A 0. 2 7 (a) 0.2

-56 28.4 0.86 89.5 0.477 71.0 43.4 0.145 44.3 16.7 Long. Weld 8-860B 0. 2 7 (a) 0.2

-56 28.4 0.50 89.5 0.276 58.1 30.5 0.084 34.3 6.7 Long. Weld 8-860C 0. 2 7 (a) 0.2

-56 28.4 2.16 89.5 1.192 93.9 66.3 0.363 64.4 36.8 Circum. Weld 1-860 0. 2 7 (a) 0.2

-56 28.4 2.66 89.5 1.468 99.0 71.4 0.447 69.4 41.8 Circum. Weld 2-860 0.27(a) 0.2

-56 28.4 5.30 89.5 2.925 115.0 87.4 0.890 86.6 59.0 KAZ 0.18 0.2 0

19.7 6.84 76.8 3.774 103.2 122.9 1.149 79.8 99.5 Ca)

Conservative estimate -

no analysis available.

b) Initial Reference Temperature measured or generic mean value per 10CFR 50.61(b)(2)(i).

Margin to be added to cover uncertainties per Regulatory Guide 1.99 Rev. 2, Section 2.1 for plates, 10CFRSO.51(b)(2)(i)

Generr:

m-ean value margin for welds.

(d) Reference 6.

(e)

Chemistry Factor determined per Regulatory Guide 1.99 Rev.

2. Section 2.1 using SONGS 1 surveillance data.

DWO.

NO.

ATTACHMENT 2