ML20198J520

From kanterella
Jump to navigation Jump to search
Pressure Temp Limits Rept (Ptlr)
ML20198J520
Person / Time
Site: Byron  Constellation icon.png
Issue date: 01/07/1998
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20198J090 List:
References
NUDOCS 9801140149
Download: ML20198J520 (24)
v • d • e


Text

. _

1 i

i i

i i

5 i

HYRON UNIT 2 i

PRESSURE TEMPERATURE LIMITS REPORT (PTLR)

(Rniwd January 7,1998) r e

i t

i 1

P A

54:

P PDR i

BYRON o UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section Page

.1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR). I 2.0 Operating Limits 1

2.1 RCS Pressure and Temperature (P/T) Limits 1

2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints 2

2.3 - LTOP linable Temperature 2

2.4 Reactor Vessel 13oltup Temperature 3

2.5 Reactor Vessel Minimum Pressurization Temperature 3

3.0 Reactor Vessel Material Surveillance Program 9

4.0 Supplemental Data Tables 11 5.0 References 18 Attachment WCAP 14824, Revision 2 "flyron Unit i Ileatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Ilyron and 13raidwood," November, 1997.

L ii

/

SYEON. UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures

}

i r

Figure Page 2.1 Hyron 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; Usmg 1996 Appendix 0 Methodology) 2.2 Hyron Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Xates S

up to 100 'F/hr) Applicable for the First 12 EFPY (Without Margins for f

instrumentation E. tors; Using 1996 Appendix G Methodology) 2.3

. Hyron Unit 2 Maximum Allowable Nominal PORY Setpoints for the Low -

7 Temperature Overpressure Protection (LTOP) System Applicable for the

'l First 12 EFPY i

k i

i 1

5 k

h r

' ill l

BYRON o UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

-I.ist of Tables Table Page 2.1 Hyron Unit 2 lleatep and Cooldown Data Poin? ~

'2 EFPY 6

(Without Margins for Instrumentation Errors) 2.2 Data Points from Byron Unit 2 PORY Setpoints for the LTOP System 8

3.1 Ilyron Unit 2 Capsule Withdrawal Schedule.

10 4.1 Ilyron Unit 2 Calculation of Chemistry Factors Using Surveillance Capsule Data 12 1.2 Hyron Unit 2 Reactor Vessel Material Properties 13 4.3

. Summary of Byron Unit 2 Adjusted Reference 'le.nperatures (ARTS) at the 1/4T 14 andL Locations for 12 EFPY 4.4

- Byron Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 15 12 EFPY at the Limit ng Reactor Vessel Material Weld Metal (Based i

on Surveillance Capsule Data)

I 4,5 RTns Values for Byron Unit 2 for 32 EFPY 16 4.6 RTers Values for Byron Unit 2 for 48 EFPY 17 iv

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

L Reference to Technical Specifications ( fS) numbers are given in both the Byron Station current-Techt.ical Specifications (CTS) and improved Technical Specifications (ITS). The CTS number is presented first, followed by the ITS number in brackets [ ).

This PTLR for Unit 2 has been prepared in accordance with the requirements of TS 6.9.1.11/[lTS 5.6.6]. Revisions to the PTLR shall be provided to tie NRC aller issuance The Technical Specifications addressed in this report are listed below:

LCO 3.4.9.1 Pressuw Temperature Limits; and LCO 3.4.9.3 Overpressure Protection Systems.

[lTS LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits; and LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System].

2.0 Operating Limits The PTLR limits for Byron Unit 2 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 of ENDF/D IV neutron transport cross-section library and ENDF/B V dosimetry reaction cross-sections,

b. Optional use of ASME Code Section XI, Appendix G, Article G-2000 1996 Addenda, c.

Use of ASME Code Case N-514, and

d. Use of RELAP computer code for calculation of LTOP setpoints for Byron Unit I replacement steam generators.

WCAP-14824, Revision 2,6 included as an attachment for reference. WCAP-14824, Rev. 2 t

conteins !be PA' curves for Byron Unit 1, along with the weld metal data integration for Byron and Braiowood Units I and 2 and th Byron /Braidwood fluence methodologyjustification for ENDF/B-VI cm wdons. WCAP-14940 (Ref,14) contains the Byron Unit 2 Heatup and l

Cooldown LirM f%n a applicable to 12 EFPY, 2.1 RCS Pressure and Temperature (PA') Limits (LCO 3.4.9.1/ [lTS-LCO 3.4.3])

2.1.! The RCS temperature rate-of-change limits defined in Reference 14 are:

l a.

A maximum heatup of 100 F in any 1-hour period,

b. A maxir im cooldown of 100 F in any 1-hour period, and A maximum temperature change ofless than or equal to 10 F in any 1-hour period c.

during insenice hydrostatic and leak testing operations above the heatup and cooldown limit curves 1

~

- HYRON - UNIT 2 -

PRESSURE AND TEMPERATURE lMITS REPORT Operating Limits (continued) 2.12 The RCS P/T limits for heatup, inservice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.1. The RCS_ P/f limits for cooldown are shown in Figure 2.2 and Table 2.1. These limitr are defined in Reference 14. Consistent with the methodology described in Reference 1, the RCS P/T li: nits Sr heatup and cooldown shown in Figures 2.1 and 2.2 are provided without margins for instrument error. These limits were developed using ASME Code Section X: Anaeadix 0. Article G-2000,1996 Addenda. The criticality limit curve specifies pressure-emperature limits for core operation to provide additional margin during actual power production as specihed in 10 CFR 50,' Appendix G.

The Pff limits for core operation (except for low power physics testing) are that the reactor vessel must be at a temperature equal to or hipher than the minimum tempirature required for the inservice hydrostatic test, and at least 40 F higher than the minimum permissible temperature in the corresponding P/T curve for heatup and cooldown.

2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints (LCO 3.4.9.3/

- [lTS-LCO 3.4.12]).

The power operated relief valves (PORVs) shall each have maximum lifl settings in accordance with Figure 2.3 and Table 2.2. These limits are based on References 5,13 and 15. The Residual Heat Removal (RH) Suction Relief Valves are also analyzed to individually provide low temperature overpressure protection. This analysis for the RH Suction Relief Valves remains valid with the current Appendix G limits contained in this PTLR document and will be reevaluated in the future as the Appendix G limits are revised.

The LTOP setpoints are based on P/T limits which were established in accordance with 10 CFR 50, Appendix G without allowance for instrumentation error and 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 Enable Temperature

- The as-analyzed LTOP enable temperature is 200*F (Reference 16).

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

(Byron Unit 2 procedures governing 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).

4 L

2 i

L

5 BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

. Operating Limits (continued)

Note that the test LTOP PORY segment in Table 2.2 extends to 450*F where the.

pressure setpoint is 2350 psig. This is intended to prohibit PORY lift for an inadvertent

~

LTOP system arming at power.

2.4 Reactor Vessel Boltup Temperature (Non-Technical Specification)

The 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 stud, and with the RCS vented to atmosphere (Reference 2).

2.5 Reactor Vessel Minimum Pressurization Temperature (Non-Technical Specification)

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 temperature instrument, determined using a technique consistent with ISA-S67.04-1994.

t

)

3

y BYRON k UNIT 2L l

a

PRESSURE AND TEMPERATURE LIMITS REPORTi O

.i

- MATERIAL PROPERTY BASIS-LIMITING MATERIAL: CIRCUMFERENTIAL WELD (using svu. sepsule data)

- LIMITING ART VALUES AT 12 EFPYf 1/4T. 87.6*F,

i 3/4T,71.5'F j

?

d 2500-9 1

.a

!.i i

e is ii s t

i.

4 i

, e i i

is i

i, g

?2250

/

/

LEAK-TEST LIWif 7 -

J r

1 i

.s I

I I

e

+s y)

..I I

I i

t

,*' 2000 l

/

l e

I I

e.*

1750 l

O - _ - -

U ACCEPTA3 E s

. OPERATION i

is r

_. 1500z

/

/

! :j En s

i s i

,e U

'l NEATUP Raft yk

[

l' 1250 vP To.-i o n r/s,.

Acc:PtAtte 0* ERAT 10N 4-1 1

,.4 s

_ 1000 _

l l

ll 1,

m

..s s

i s

t i

e.

  • O e

e i

4 6

s 750 l

l l

~

. e s e

-5_0 0

[!

f~

m O

6 4

wm i.

e..

4 e

i 7

250~

Boitup C5ttlCALITY limit BASBS SM al Temp.-

inesse::: syssesta ic tas, touP:natvas sis r -ren ts:-

)

88StICS PSSle(t-WP 0 38.0 ErPY i**

I I ',' ',

p 0

0

- 50 100 150 200 250 300 350 4$0

-450 500 M o d e r a tio'r Tempe!rature-(-- D e g. F )

Figure 2.1

Byrom Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 100 'F/hr) 4 1

g e

1 Applicable for the First 12 EFPY (Without Margins for Instrumentation Errors) 4 s

4 9--au-w,,

~g i,99

,s.

u-w w.. -,

_,4a,,.,

,,ww-.

,..-..,..---m.,_w..,._,y-..

us

.,--,m

+..

4 5

' B RON - UNIT 2 FRESSURE AND TEMPERATURE LIMIM REPORT =

MATERIAL PROPERTY BASIS

- i

' LIMITING MATERIAL: CIRCUMFERENTIAL WELD. (voing surv. capsule date)

LIMITING ARTVALUES AT 12 EFPY
-

il4T. 87.6'F j

'3/4T, 71.5'F a

l 1

4 2500 1

si...

I e

i f

6 I

.e e

i.

,4,

~u:2250 i

6 iu

. ui -

.6

=.2000 i

e i

i 4,,

t ii..

.i

, ;i ie

=

6 e

i i

i i

i I

7 6 4

. e i

,,t t

1750 uNaccrPrants 4

i U

e., OPERATION r

i.

a 4,, e eii y-t

, i. i

.i 7

1500

. u2 r

s n

i..i e

r i,

i i

.,r, i

i.

i U.1250 a c c i, r i e s. g f

i g

I OPERATION c,,,

i e -

/

1000 i

e C00LD0VN l

l l' l

U 750 -: EN

l '.::

re -

e

, ii

.i,.

i..

I e

v

,!,=

m 500 2

i i i i

i O

g i

m 250 g

-g Temp.

i.

0 200 250 300 350 400 450 500 i

0 50.

100

.150

.M o d e r..a t o r Temperature (De.g.F)

]

Figure 2.2 Byron Unit 2 Reacter Coolant System Cooldown Linnitations (Cooldown Rates up to 100 *F/hr)

- Applicable for the First 12 EFPY (Without Margins for lustrumentation Errors) 5 1

d

.-4 i-

~e,,

w

=.m.-

--m..

--,m,,,-.,.....,..%..

.r.-

w

-r,--,

BYRON o UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT -

Table 2.1 Byron Unit 2 Heatup and Cooldown* Data Points at 12 EFPY"'

(WMhout margins for instrumentation errors)

HEATUP CURVES COOLDOWN CURVES 100 F Hatup L..k T.1 Curv.

Cr60cahty L6mit umit steady State 25 DEO F 80 DEG F 100 UE0 F T

P T I P T i P T I P T t P T i P T I P

- 60 0

212 0

191 2000 60 0

60 0

60 0

60 0

60 621 212 649 212 2485 60 621 60 589 60 538 60 437

_.,_6 5

75 621 212 669 75 621 75 (G

75 581 75 486 80 621 212 662 80 621 80 621 80 597 80

- 505 85 621 212 658 85 621 85 621 85 614 85 526 90 621 212 657 90 621 90 621 90 621 90 548 95 621 212 650 95 621 95 621 95 Cli 95 572 100 621 212 663 100 621 100 621 100 621 100 599 105 621 212 670 105 621 105 621 105 621 105 621 110 621 212 679 110 621 110 621 110 621 110 621 115 621 212 690 115 621 115 621 115 621 115 621 120 621 212 703 120 621 120 621 120 621 120 621 125 621 212 719 125 621 125 621 125 621 125 621 130 621 212 738 130 621 130 621 130 621 130 621 135 621 212 758 135 621 135 621 135 621 135 621 140 621 212 781 140 621 140 621 140 621 140 621 145 621 212 507 145 621 145 621 145 621 145 621 150 621 212 635 150 621 150 621 150 621 150 621 150 738 215 866 150 1045 150 1028 150 1016 150 1006 j

155 758 220 900 155 1087 155 1074 155 1066 155 1066 160 781 225 937

~

160 1132 160) 1123 16r5 1120 160 1131 165_,80(,]_, {d 165 1180 165 117i _165_1177 )_

170 835 235 1021 170 1232 175 866 240 1068 175 1288 180 _.

900 245 1119 180 1349 165 937_

250 1174 185 1413 190

-977 255 1733 190 1483

.95 1021 280 1297 195 1558 200 1068 265 1366 200 1638

_205 _

-275 1521 210 1818 1119 270 1441 205 1725_

210 1174 215 1233 280 1607 215 1918

~

~

~

~

1 1

2 4

230

- 1441 295 1905 230 2266 235 1521 300 2020

-235 2400 3

240 1607 305 2143 245 1699 310 2275 250 1798 315 2417 255 1905 260 2020 L__

265 2143 j~

i l

270 2275 l

I i-275 2417 i

" For each c00ldown rate, the steady-state pressure values shall govern the temperature where no allowable pressure values are provided

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT eso _

___._____7__._____.

_m__

_s i._._

_ UNACCERTABLE_

_- iJ_LLk' Y1L'LG"__-__

600 -

^ - - -

__2.__.._..

_ ____.J_._.q._

i

s

__.l _.- --.-

y_

s. --

re_vc4ss.._.____ ___

_L,__.--_._.-_Lq 1

e

._.. _~

_ m g

._q__

. _.[._.

_,1Q\\(-455A'_.j_.

g

__._. =

, soo

._m

_ __.L

_.. g y.,9 -

a

-__y.

.y..

__.-_-._-a_.+.

[

_._p.y __A

.ACCER.TABL g

- _4--

3.-.___-

4so p.

q.__._

l.__L

._..4...

___.J.A w

__. ___.____T___

_i___. _.____

J..

r*~

~

r.

.t_.J

_t

_g_ dbl-A

--.___4 400 d -

J-J~

d---

k--

4 l_ -

0 60 100 160 200 260 300 360 400 AUCTIONEERED LOW RCS TEMPERATURE (DEG. F)

Figure 2.3 i

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

1

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.2 Data Points for Byron Unit 2 Maxiinuin Allowable PORY Setpoints for the LTOP System Applicable for the First 12 EFPY*

PCV-455A PCV-456 l2TY 0413M)

(2TY-0413P)

AUCTIONEERED LOW RCS PRESSURE AUCTIONEERED LOW RCS PRESSURE RCS TEMP. (DEG. F)

(PSIG)

RCS TEMP. (DEG. F)

(PSIG) 50 497 50 514 70 497 70 514 100 497 100 514 120 446 120 462 150 446 150 462 200 446 200 462 250 587 250 604 300 587 300 604 350 587 350 604 450 2350 450 2350 Note: To determine ineximnin 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

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT -

3.0 Reactor Vessel Material Surveillance Program

~ The reactor vessel material irradiation surveillance specimens shall be removed and analyzed to -

determine changes in material properties. The removal schedule is provided in Table 3.1. Also, 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 refuehng outages or reactor shutdowns most closely approaching the withdrawal schedule.

The pressure vessel material surveillance program (Reference 6)is in compliance with Appendix 11 to 10 CFR 50," Reactor Vessel Radiation Surveillance Program." The material test -

requirements and the acceptance standard utilize the reference nil-ductility temperature, RTwr, which is determined in accordance with ASME Sec' ion III, NB-2331. The empirical

. relationship between RTwr and the fracture toughness of the reactor vessel steelis developed in accordance with Appendix G," Protection Against Non Ductile Failure," to Section XI of the ASME F3 oiler and Pressure Vessel Code. The surveillance capsule removal schedule meets the requirements of ASTM E185-82.

L

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT -

Table 3.1

~ Byron Unit 2 Capsule Withdrawal Schedule Capsule Vessel Location -

Capsule Lead Removal Time"'

Estimated Capsule 2

(Degrees)

Factor (EFPY)

Fluence (n/cm )

U 58.5*

3.96 1.15 (Removed) 3.996 x 10" W

121.5*

3.89 4.634 (Removed) 1.211 x 10" X

238.5*

3.89 8.23 (EOL Wall) 2.192 x 10"'

12.34(1.5 EOL Z

301.5*

3.89 Wall"))

3.288 v.10" V

- 61.0*

3.64 Standby

-Y 241.0 3.64 Standby (a) Effective Full Power Years (EFPY) from plant stanup.

(b) Maximum end oflicense (32 EFPY) inner sessel wall fluence.

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

t i

10

BYRON - UNIT 2 -

PRESSURE AND TEMPERATURE LIMITS REPORT

-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 P/T limits.

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

Table 4.2 provides the reactor vessei material properties table.

Table 4.3 provides a summary of the Byron Unit 2 adjusted reference temperature (ARTS) at the l/4T and 3/4T locations for 12 EFPY.

Table 4.4 shows the calculation of ARTS at 12 EFPY for the limiting Byron Unit 2 reactor vessel material weld metal (Based on Surveillance Capsule Data).

- Table 4.5 provides RTers values for Byron Unit 2 for 32 EFPY, Table 4.6 provides RTers alues for Byron Unit 2 for 48 EFPY.

v 1I

i HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.1 Calculation of Chemistry Factors 'Jsing Surveillance Capsule Data Fluence Material Capsule (n/cm,

FF"'

Measured FF*ARTxur (FF)2 2

E> l.0 -

ARTmn Mev), f Lower Shell.

Forging 49D330/

U 3.996x 10

O.746 0

0 0.556 49C298 1 (Tangential)

W l.211x 1O '

l.053 5

5.267 1.I10 l

Lower Shell Forging 49D330/

U 3.996x10

O.727 25 18.65 0.556 49C298 1 -1 (Axial)

W l.211 x 10

l.053 40 32.73 1.I10 Sum:

66.037 3.332 Chemistty Factor (d' = 66.037 + 3.332 = 19.8*F Byron 1 Weld Metal WF-336"

U 3.72x10'8 0.727 0

0 0.00 0.529 X

1.39x 10

l.091 35 105"'

114.56 1.190 Byron 2 Weld Metal WF-447")

U 3.996x10

O.746 0

0 0

0.557 W

l.211 x 10

l.,053 30 90"'

94.77 1.I10 Sum:

209.33 3.386 Chemistry Factor 'd' = 209.33+3.386= 61.8'F (a) FF = Fluence Factori fonai %o (b) Byron Unit 1 ARTmyr values were obtained from the surveillance Capsule X analysis (WCAP 13880, Refercuce 10).

The Byron Unit I capsule fluence values were recalculated using the ENDF/B-V scattering cross sections in 1994 and are documented in WCAP 14044 (Reference 8).

(c) Byton Unit 2 capsule Quence, FF, and ARTmn alues were obtained from the surveillance Capsule W analysis of I

v WCAP-14064 (Reference 3) using the ENDF/lW scattering cross sections.

(d) Chemistry Factor = E (FF*ARTmn) / E ((FF)2)

(e)- Adjusted ARTmn per Ratio Procedure of Regulatory Guide 1.99, Rev. 2 (Ref.12). Ratio = 3.0. See Table 2 of WCAP 14824. Rev. 2,-(Ref. 2). Actual ratio is 2.5 (68.0/27.0 = 2.5); However, for conservatism, ratio of 3.0 was used.

12

-=

. -. -. ~ -

BYRON - UNIT 2

- PRESSURE AND TEMPERATURE LIMITS REPORT-Table 4.2 Byron Unit 2 Reactor Vessel Material Properties i

Material Description Cu (%)"'

Ni ('d)

Chemistry initial Factor"'

RT mn ('F)*'

Closure Head Flange Not -

0.74 0")

-i Reported Vessel Flange Not 0,73 30")

Reported Inter. Shell Forging 0.01 0.70 20.0

-20 49D329/49C297-1-1.

Lower Shell Forging 0.05 0,71 32.2

-20 49D330/49C298-1-1 Circumferential Weld 0.05 0.62 68.0 10 WF-447 l

a) Chemistry Factors are calculated from Cu and Ni values per Regulatoly Guide 1.99, Rev. 2 (Reference 12).

Initial RTum alues are measured, WCAP 14063 (Reference 7) b)

v Closure head and vessel flange Initial RTum alues are used for considering flange requirements for the c) v heatup/cooldown curves, WCAP-14940 (Reference 14).

13

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 4,3 Summary of Byron Unit 2 Adjusted Reference Temperatures (ARTS) at 1/4T and 3/4T Locations for 12 EFPY 12 EFPY Material Description 1/4T ART (*F) 3/4T ART ( F)

Intermediate Shell Forging 12.1 1.7 49D329/49C297-1-1 (R G.1.99 Position 1 ()

Lower Shell Forging 31.7 14.9 49D330/49C298-1-1 (RG Position l)

Using capsulc data i 1.8 1.5 (RG Position 2()

Circumferential Weld 119.2 83.7 WF-447 (RG Position 1()

Using credible surveillance 87,6*'

71,5*'

capsule data (RG Position 2('))

(a) Calculated using a chemistry factor based on Regulatory Guide (RG) 1.99, Positions I and 2 (Reference 12). Note that surycil!ance data for lower shcIl forging was detennined to be NOT credible per WCAP-14824, Rev. 2, itowever, the results are reported here for completeness.

(b) These ART values were used to generate the Byron Unit 2 Heatup and Cooldown Cunes, WCAP-14940 (Reference 14).

I4

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Tahic4.4 Hyron Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 12 EFPY at the Limiting Reactor Vessel Material-Weld Metal (Based on Surveillance Capsule Data)-

Parameter Values Operating Time 12 EFPY Location *'

1/4T ART 3/4T ART Chemistry Factor, CF (*F) 68.0 68.0 Fluence (f), n/cm 4.94x 10'"

1.78x 10

2 (E> l.0 Mev)"'

Fluence Factor, FF 0.803 0.542 ARTmr= CFxFF( F) 49.63 33.50 Initial RTmr_,1( F) 10 10 Margin, M ( F) 28.00 28.00 ART = 1+(CF*FF)+M, F 87.6 71.5 per RG 1.99, Revision 2 (a) Fluence, f, is based upon for (E>l.0 Mev) = x.22x 10" at 12 EFPY, WCAP.14940 (Reference 14).-

(b) The By ron Unit 2 reactor vessel wall thickness is 8.5 inches at tir; beltline region.

15

HYRON - UNIT 2

+

PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.5

..RTns Values for Hyron Unit 2 for 32 EFPY j

~

M

. RTmrtv) -

ARTns RTm CF p.>

ppi,3 Material

(*F)

(*F) -

(F)

( F)

( F)

Lower Shell Forging 32.2 2.192 1.213 34.0

-20 39.1:

53.1 MK 24 Using Surveillance-19.8 2.192 1.213

'34.0d 20 24.0 38.0 Capsule Data (

Intermediate Shell Forging 20.0 2.192 1.213 24.3

-20 24.3 28.6 MK 24-2 Circumference Weld 68.0 2.192 1.213 56.0 10 82.5 148.5 -

Metal WF447 Using Surveillance 61.8 2.192 1.213 28.0 10 75.0 113.0 Capeule Data (a) 2.192x10* nfcm (E>l.0 Mev) for 32 EFPY from Byron 2 PTS report, WCAP.i4054 (Reference 9) 3 (b) FF (Fluence Factor) = (* '"8 0 (c) Calculated using a CF based on surveillance capsule data per RG l.99, Position 2 (Reference 12).

(d) Double margin is used here due to the base metal surveillance capsule data exceeding the one sigma criteria from the -

credibility evaluation.

t O

16-

!'+e

~

BYRON - UNIT 2

! PRESSURE AND TEMPERATURE LIMITS REPORT i

Table 4.6 RTns Values for Byron Unit 2 for 48 EFPY M

RTxman ARTns RTns CF p.

ppe

- Material

(*F)

('F)

( F)

('F)

( F)

Lower Shell Forging 32.2 3.288 1.312

-34.0 20 42.2 56.2 MK 24-3 d

Using Surveillance 19.8 3.288 1.312 34.0

-20 26.0 40.0 Capsule Data")

Intermediate Shell Forging 20.0 3.288 1.312 26.2 -

-20 26.2 32.4 MK 24-1 Circumference Weld 68.0

' 3.288 1.312 56.0 10 89.2 155.2 Metal WF447 Using Surveillance 61.8 3.288 1.312 28.0 10 81,1 119.1 Capsule Data 2

(a) 2.192x10" n/cm (E>l.0 Mcv) for 32 EFPY from Byron 2 PTS report, WCAP 14054 (Reference 9). The following

_ calculation provides the 48 EFPY fluence vrdac:

2.192x10" + ((2.192x10" 3.174x10")/32-4.634 EFPY)) * (48 32 EFPY) = 3.288x10" n/cm (b) FF (Fluence Factor) = ("2""*'"""

(c) Calculated using a CF based on surveillance capsule data per PG l.99, Position 2 (Reference 12).

. (d) Double margin is used here due to the base metal surveillanw asule data exceeding the one sigma criteria from the credibility evaluation.

17 l

s

HYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 5.0 --

Ref'erences 1.

WCAP-14040-NP A, Revision 2," Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Andrachek, J.D., et. al., January 1996.

2.

WCAP-14824, Revision 2 " Byron Unit i lieatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Byron & Braidwood,"

November,1997 plus Westinghouse errata letters CAE-97-220, dated November 26, 1997 and CAE-97-231 and CAE-97 233, dated January 6,1998, 3.

WCAP-14064," Analysis of Capsule W from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program," Malone, M.J., et al., July 1994.

4.

WCAP 12431," Analysis of Capsule U from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program," Terek, E., et al., October 1989 5.

Westinghouse Letter to Commonwealth Edison Company, CAE-96-106," Byron Unit I and 2 LTOPS Setpoints Based on 10 and 12 EFPY P/T Limits," January 17,1996.

WCAP-10398," Commonweal h Edison Company, Byron Station Unit 2 Reactor Vessel 6.

t Radiation Surveillance Program," Singer, L.R., December 1983.

7.

WCAP-14063," Commonwealth Edison Company, Byron Unit 2 Ileatup and Cooldown Limit Curves for Normal Operation," Peter, P. A., November 1994.

8.

WCAP-14044, " Westinghouse Surveillance Capsule Neutron Fluence Reevaluation,"

Lippencott, E.P., April 1994.

9.

WCAP 14054," Evaluation of Pressurized Thermal Shock for Byron Unit 2," Peter, P.A., August 1994.

10. 10 CFR Part 50, Appendix G," Fracture Toughness Requirements," Federal Register, Volume 60, No. 243, dated December 19,1995.
11. 10 CFR 50.61," Fracture Toughness Requirements for Protecion Against Pressurized Thermal Shock Events," _(PTS Rule) May 15,1991.
12. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99," Radiation Embrittlement of Reactor Vessel Materials," Revision 2, May 1988.

18

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT j

Ref'erences (continued)

13. Comed Calculation BRW-96-9071/BYR 96-294," Channel Accuracy for Power Operated Relief Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit 2 Original Steam Generators)" Revision 0, 14; - WCAP-14940," Byron Unit 2 Heatup and Cooldown Limit Curves for Normal Operation," Laubham, T. J., et al., October,1997 plus Westinghouse errat letters CAE-97 201 dated November 4,1997 and CAE-97-231 and CAE-97-232 dated January 6,1998.
15. Westinghouse Letter to Comed, CAE-97 202," Byron Unit 2 COMS Setpoints for 12 EFPY," October 23,1997,
16. ' Westinghouse Letter to Comed, CAE-97-211/CCE-97-290, " Byron and Braidwood Units 1 and 2 ATmetal Evaluation," November 7,1997, 19 w.

ATTACilMENT WCAP-14824, REVISION 2, HYRON UNIT I IIEATUP AND COOL,DOWN 1,IMIT CURVES FOR NORMAL OPERATION AND SURVEILLANCE WELD METAL, INTEGRATION FOR BYRON AND BRAIDWOOD 1

--

Retrieved from "https://kanterella.com/w/index.php?title=ML20198J520&oldid=4097885"