ML20207B523

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Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016
ML20207B523
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 11/30/1986
From: Berryman R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18149A442 List:
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-59988, TAC-59989, NUDOCS 8612030034
Download: ML20207B523 (19)
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NORTH ANNA UNITS 1 and 2 REACTOR VESSEL FLUENCE AND RT PTS EVALUATIONS SUPPLEMENT TO WCAP 11016 Prepared by NUCLEAR ENGINEERIN'i ENGINEERING AND CONSTRUCTION DEPARTMENT VIRGINIA ELECTRIC AND POWER COMPANY November, 1986 APPROVED BY: 0 7d bl3 [# kl$ /IbdG Date APPROVED BY: ywa //!2 4 Date 8612030034 861126 PDR ADOCK 05000280 P PDR

CLASSIFICATION / DISCLAIMER The data, information, analytical techniques, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company. (the Company), and they may not be appropriate for use in situations other than those for which they were specifically prepared.

The Conpany therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF. DEALING. 0R USAGE OF TRADE, with respect to this report or any

- of the data, information, analytical techniques, or conclusions in it.

By making this report available, the Company does not authorize its use 4 by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arisi g out of the use, authorized or unauthorized, of this report or the data, information, and analytical techniques, or conclusions in it.

11

TABLE OF CONTENTS 1.0 Introduction .......................... 1 2.0 Fluence and RT pts Methodology ................ 1 2.1 Fluence Calculations ..................... 1 2.2 RT pts Formulation ...................... 3 3.0 Supplemental Fluence and RT pts Results ............ 4 4.0 Conclusions ......................... 15 5.0 References .......................... 16 l

i Supplement To WCAP 11016 Page 111 i

A - 2: .-- 4 4- A  % n - 6

1.0 INTRODUCTION

Pursuant to 10 CFR 50.61, the Virginia Electric and Power Company provided a submittal of the values of the current and projected reference temperatures for pressurized thermal shock (RTpts) for Units 1 and 2 of the North Anna Power Station on January 23, 1986. As required in 10 CFR 50.61(b)(1), the projected values were determined up to the time of the expiration date of the current operating licenses (i.e. 40 years from the date of issuance of the construction permit).

The purpose of this report is to provide the projected reference temperature for pressurized thermal shock (RTpts) values for North Anna Units 1 and 2 for approximately 40 and 60 years of operation. Section 2 discusses the methodology used to extend the RT estimates. Section 3 pt, presents the supplemental results. Conclusions are presented in Section 4.

2.0 FLUENCE AND RT PTS METHODOLOGY 2.1 FLUENCE CALCULATIONS Fast neutron exposure calculations were performed for the North Anna reactor vessel model which included the reactor core, the baffle, the core barrel, the thermal shiold, and the reactor pressure vessel. Two sets of Supplement To WCAP 11016 Page 1

i a

transport calculations were performed. First, a single foreward mode calculation was performed which provided the neutron energy spectrum.

Second, a series of adjoint analyses relating the neutron flux > 1.0 MeV at several locations within the reactor geometry to the power distributions

! within the core. These adjoint importance functions when combined with cycle specific core power distributions yield the plant specific exposure data for each operating cycle.

The forward and adjoint calculations were carried out using the DOT discrete ordinates code and the SAILOR cross-section library. The adjoint source locations were chosen at the center of each of the surveillance capsules and at positions along the inner radius of the pressure vessel.

Core power distributions for use in the plant specific fluence evaluations for North Anna Units 1 and 2 were derived from assembly and cycle average burnups for each operating cycle to date for the two

, reactors. These data were used to project neutron fluence for each unit for ,pproximately 40 and 60 years of operation. ,

Several assumptions were made in order to accomplish the fluence projections. An 80*. capacity factor was assumed for all cycles beyond the current cylce. Tbc low leakage loading pattern was assumed for all cycles l beyond the current cycle. Finally, a North Anna core uprating to the pcwer level used in the safeguards analysis (i.e.2893 MWt) was assumed for each i

l unit. The methods, data and assumptions used in the projection of fluence are the same as those used in Reference 1.

l j

i l Supplement To WCAP 11016 Page 2 l

I

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^ 2.2 RTPTS FORMULATION The PTS rule requires that a specific. formulation be used to determine the transition temperature. The transition temperature must be calculated for each weld .md forging within the beltline region of the reactor vessel.

The results of the calculation are compared to specified screening criteria to determine which specified action is required. For each material, the RT is the lower of the results given by Equations 1 and 2 (i.e. with pt, the same material property data as Reference 1).

1 Equation 1:

i RT pg3 = I + M + (-10 + 470(Cu) + 350(Ni)](f)0.270 Equaticn 2:

l RT pts = I + M + 283(f)0.194 i

j where r

s I E The intial reference transition temperature of the unirradiated material measured as defined in the ASME Code.

M E The margin to be added to cover uncertainties in the values of initial RTndt, copper and nickel content, fluence, and calculation procedures.

i Cu,Ni E The best estimate weight percent of copper and nickel in the material.

f E The best estimate neutron fluence, in units of 10" .

Supplement To WCAP 11016 Page 3 4

' - , . , , . . - - , . , , - . . _ _ . ~ _ . . . - - . , . . , , , . ~ , , , _ _ - - m...._.._--..,,.m .-, - ,,.. -,m ._..,v.. - -

3.0 SUPPLEMENTAL FLUENCE AND RTPTS RESULTS The calculated fast neutron fluence for each of the North Anna units are presented in tables 3-1 through 3-8. Data are presented at several azimuthal locations on the inner radius of the vessel. These locations were chosen to coincide with the locations of the surveillance capsules which are located at 0,15,25 and 45 degree azimuths.

The RT results are presented in figures 3-1 and 3-2 for North Anna pts Units 1 andg2 respectively. These figures indicate the limiting weld and forging rel tive to the screening criteria. As the figures indicate, the earlier resu(lts from Reference 1 are presented along with the supplemental data for 40 t.nd 60 calender years of operation.

l 6

Supplement To WCAP 11016 Page 4

Table 3-1 NORTH ANNA UNIT 1 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 0' AZIMUTHAL ANGLE (a)

Elapsed Cumulative Fluence (n/cm")

Irradiation Irradiation Avg. Flux Plant Design 2

Interval Time (EFPY) (n/cm -sec) Specific Basis (b) 2/18/2011 + 11/26/2017(c) 30.4 3.71 E 10 3.74 E 19 6.73 E 19 11/26/2017 + 11/26/2037(d) 46.4 3.71 E 10 5.62 E 19 1.03 E 20 (a) Applicable to the peak azinuthal locations (0', 90', 180' and 270') on the core beltline (h) tesign basis fast neutron flux = 6.78 E 10 n/cm*-sec~at

.775 MWth.

(c) L /26/2017 l corresponds to 40 calender years beyond issuance of the fuel load license.

(d)'11/26/2037 corresponds to 60 calender years beyond issuance of the fuel load license.

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i Supplement To WCAP 11016 Page 5

Table 3-2 NORTH ANNA UNIT 1 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 15' AZIMUTHAL ANGLE Elapsed Cumulative Fluence (n/cm*)

Irradiation Irradiation Avg. Flux Plant Design Interval Time (EFPY) (n/cm -sec) Specific Basis (a) 2/18/2011 + 11/26/2017(b) 30.4 1.84 E 10 1.85 E 19 3.07 E 19 11/26/2017 + 11/26/2037(c) 46.4 1.84 E 10 2.78 E 19 4.70 E 19 (a) Design basis fast neutron flux = 3.09 E 10 n/cm*-sec at 2775 MWth.

(b) 11/26/2017 corresponds to 40 calender years beyond issuance of the fuel load license.

(c) 11/26/2037 corresponds to 60 calender years beyond issuance of the fuel load license.

Supplement To WCAP 11016 Page 6

. _ ~_ _ . . .

e f

Table 3-3 NORTH ANNA UNIT 1 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE  :

VESSEL INNER RADIUS - 30' AZIMUTHAL ANGLE Elapsed Cumulative Fluence (n/cm")

Irradiation Irradiation Avg. Flux ' Plant Design Basis (a)

Interval Time (EFPY) (n/cm"-sec) -Specific 2/18/2011 + 11/26/2017(b)30.4 1.05 E 10 1.04 E 19 1.80 E 19 11/26/2017 + 11/26/2037(*)46.4 1.05 E 10 1.57 E 19 2.75 E 19 4 .

\

a (a) Design basis fast neutron flux = 1.81 E 10 n/cm 8 -sec at 2775 MWth.

e (b) 11/26/2017 corresponds to 40 calender years beyond issuance l of the fuel load license.

-(c) 11/26/2037 corresponds to 60 calender years beyond issuance of the fuel load license.

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l f Supplement To WCAP 11016 Page 7

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Table 3-4 NORTH ANNA UNIT 1 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 45' AZIMUTHAL ANGLE Elapsed Cumulative Fluence (n/cm*)

Irradiation Irradiation Avg. Flux Plant Design Interval Time (EFPY) (n/cm -sec) Specific Basis (a) 2/18/2011 + 11/26/2017(b) 30.4 7.28 E 9 7.14 E 18 1.09 E 19 11/26/2017 + 11/26/2037(c) 46.4 7.28 E 9 1.08 E 19 1.66 E 19 (a) Design basis fast neutron flux = 1.10 E 10 n/cm -sec at 2775 MWth.

(b) 11/26/2017 corresponds to 40 calender years beyond issuance of the fuel load license.

(c) 11/26/2037 corresponds to 60 calender years beyond issuance of the fuel load license.

Supplement To WCAP 11016 Page 8

Table 3-5 NORTH ANNA UNIT 2 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 0' AZIMUTHAL ANGLE (a)

Elapsed Cumulative Fluence (n/cm8 )

Irradiation Irradiation Avg. Flux Plant Design Interval Time (EFPY) (n/cm8 -sec) Specific Basis (b) 2/19/2011 + 8/21/2020(c) 31.4 4.48 E 10 4.47 E 19 6.96 E 19 8/21/2020 + 8/21/2040(d) 47.4 4.48 E 10 6.73 E 19 1.05 E 20 (a) Applicable to the peak azimuthal locations (O', 90', 180' and 270') on the core beltline.

(b) Design basis fast neutron flux = 6.78 E 10 n/cm 8 -sec at 2775 MWth.

(c) 8/21/2020 corresponds to 40 calender years beyond issuance of the operating license.

(d)'8/21/2040 corresponds to 60 calender years beyond issuance of the operating license.

Supplement To WCAP 11016 Page 9

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Table 3-6 t

NORTH ANNA UNIT 2 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 15' AZIMUTHAL ANGLE Elapsed Cumulative Fluence (n/cm*)

Irradiation Irradiation Avg. Flux Plant Design Interval Time (EFPY) (n/cm8 -sec) Specific Basis (a) ,

2/19/2011 + 8/21/2020(b) 31.4 2.24 E 10 2.24 E 19 3.17 E 19 8/21/2020 + 8/21/2040(c) 47.4 2.24 E 10 3.37 E 19 4.80 E 19 Y

i (a) Design basis fast neutron flux = 3.09 E 10 n/cm8 -sec at 2775 MWth.

(b) 8/21/2020 corresponds to 40 calender years beyond issuance

of the operating license.

1' (c) 8/21/2040 corresponds to 60 calender years beyond issuance of the operating license.

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i Supplement To WCAP 11016 Page 10 1

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Table 3-7 i NORTH ANNA UNIT 2 FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 30' AZIMUTHAL ANGLE I

Elapsed . Cumulative Fluence (n/cm8 )

Irradiation Irradiation Avg. Flux Plant Design Interval Time (EFPY) (n/cm8 -sec) Specific Basis (a) 2/19/2011

  • 8/21/2020(b) 31.4 1.30 E 10 1.30 E 19 1.85 E 19 8/21/2020 + 8/21/2040(c) 47.4 1.30 E 10 - 1.96 E 19 2.80 E 19 i

(a) Design basis fast neutron flux = 1.81 E 10 n/cm 8 -sec at 2775 MWth.

(b) 8/21/2020 corresponds to 40 calender years beyond issuance of the operating license.

, (c) 8/21/2040 corresponds to 60 calender years beyond issuance of the

operating license.

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i Supplement To WCAP 11016 Page 11 1

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Table 3-8 NORTH ANNA UNIT 2

-FAST NEUTRON (E > 1.0 MeV) EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 45' AZIMbTifAL ANGLE

. Elapsed Cumulative Fluence (n/cm2 )

Irradiation- _ , Irradiation Avg. Flux Plant Design.

Interval' Time (EFPY) (n/cm*-sec) Specific Basis (a) 2/19/2011 + 8/21/2020(b) 31.4 9.17 E 9 9.13 E 18 1.12 E 19 8/21/2020 + 8/21/2040(c) 47.4 . . 9.17 E 9 1.38 E 19 1.70 E 19

'\

(a) Design basis fast neutron flux = 1.10 E 10 n/cm'-sec at

'2775 MWth.

(b) 8/21/2020 corresponds to 40 calender years beyond issuance of'theEoperating: license.

(d) 8/21/2040 corresponds-to 60 calender years beyond issuance of the operating license.

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. g Supplement To WCAP 11016- Page 12

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-. FIGURE 3-1 NORTH ANNA UNIT 1 - RT PTS CURVES PER PTS RULE METHOD [1] DOCKETED 2 BASE MATERIAL AND WOG DATA BASE MEAN WELD MATERIAL PROPERTIES, a

O

. r NRC SCREENING VALUE FOR CIRCUMFERENTIAL WELDS g , m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

M ;NRC SCREENING _VALUE FOR FORGINGS _ _ _ _ _ _ _ __ _ _ _ _ _

{

{

E 260 -

240 -

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220 -

200 - I I

LIMITING FORGING (LOWER SHELL) l nis0 -

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CIRCUMFERENTIAL WELD 8 120 -

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, FLIE80CE. IEUTDOIIS / CMI i

O Present (4.7 EFPY) 3 License Expiration (25.0 EFPY) a 60 Yaare pounnd Tee.anco nf n (AA A rrov)

FIGURE 3-2 l^ NORTH ANNA UNIT 2 - RTpre CURVES PER PTS RULE METHOD [1]

u

"- DOCKETED BASE MATERIAL AND WOG DATA BASE MEAN WELD MATERIAL

$ NRC SCREE g m _ _ _ _ _ NING VALUE FOR CIRCUMFERENTIAL WELDS 289 NRC SCREENING VALUE FOR FORGINGS g -_______ _ __ __ ________-----

g aos - ,

f 249 -

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g 1918 to

ion FLMNK. IENTReus / CIB2 o Present (3.5 EFPY) e License Expiration (23.8 EFPY) 60 Years Beyond Issuance of 0.L. (47.4 EFPY) 4

4.0 CONCLUSION

S 1

. The supplemental data indicate that no weld or forging from either of

' the North Anna units violates the PTS screening criteria at any time up to sixty calender years of operation. The limiting material is the Unit 2 lower shell forging which has 18'F margin to the screening criteria at 60 calender years of operation.

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i Supplement To WCAP 11016 Page 15 l

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5.0 REFERENCES

1. Furchi, E.L. , et. al., North Anna Units 1 And 2 Reactor Vessel Fluence And RT pts Evaluations, WCAP 11016, Rev. 1, December, 1985.

Supplement To WCAP 11016 Page 16

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