Text

Pressure Temp Limits Rept (Ptlr)
	ML20198J506
Person / Time
Site:	Byron
Issue date:	01/07/1998
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20198J090	List: ML20198J083; ML20198J506; ML20198J520; ML20198J553; ML20198J564;
References
	NUDOCS 9801140145
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I RYRON UNIT 1 i

PRESSURE TEMPERATURE ,

LIMITS REPORT (PTLR)

(Hetleed January 7.199N) f i

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BYNON . UNIT 1 PRESSURE ANItTEMPERATURE LIMITS REPORT l I

i Table of Contents i

. Section Page 1

-1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) 1 2.0 Operating Limits 1 2.1. RCS Pressure and Temperature (P/T) Limits 1 l

2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints 2. !

23 LTOP Enable Temperature 2.

2.4 Reactor Verisel Boltup Temperature 3 2.5 . Reactor Vessel Minimum Pressurization Temperature 3 i

3.0 Reactor Vessel Material Surveillance Program 9 ,

t 4.0 Supplemental Data Tables 11 ,

5.0 References 18 t

Attachment WCAP 14824, Revision 2,

Byron Unit 1 Ileatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Byron and Braidwood", November i 1997.

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HYNON . UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures l Figure Page 2.1- Hyron Unit 1 Reactor Coolant System licatup Limitations (licatup Rates up to 4- ,

100*F/hr) Applicable for the First 12 EFPY (Without Margins for Instmmentation Errors) :

2.2 - Hyton Unit i Reactor Coolant System Cooldown Limitations (Cooldown Rates $

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

, 2.3 - Hyron Unit 1 Maximum Allowable Nominal PORY Setpoints for the Low 7 Temperature Overpressure Protection (LTOP) System Applicable for the First 12 EFPY !

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BYRON o UNIT I l PRESSURE AND TEMPERATURE LIMITS REPORT j I

List of Tames !

Table Page 2.1 Byron Unit i Ileatup and Cooldown Data Points at 12 EFPY 6 :

(Without Margins for Instrumentation Errors) 2.2 Data Points from Byron Unit 1 PORY Setpoints for the LTOP System 8

3.1 . Byron Unit 1 Capsule Withdrawal Schedule 10 l r

4.1 Byron Unit 1 Calculation of Chemistry Factors Using Surveillance Capsule Data 12 4.2 Byron Unit 1 Reactor Vessel Material Properties 13 f i

4.3 - Summary of Byron Unit 1 Adjusted Reference Temperatures (ARTS) at the 1/4T 14 and 3/4T Locations for 12 EFPY 4.4 Byron Unit 1 Calculation of Adjusted Reference Temperatures (ARTS) at 15 12 EFPY at the Limiting Reactor Vessel Material Intermediate Shell i Forging SP 5933 (Based on Surveillance Capsule Data) 4.5 RTns Values for Byron Unit ! for 32 EFPY 16 4.6 - RTers Values for Byron Unit I for 48 EFPY 17 4

I i

- _ _ _ . . _ - - _ _ _ _ ___ _ _ _ _~____ _.

i HYRON.(1NITI t 1

PRESSURE ANI) TEMPERATURE LIMITS REPORT i

1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

Reference to Technical Specifications (TS) numbers are given in both the Ilyron Station current ;

Technical Specifications (CTS) and improved Technical Specifications (ITS). The CTS number ;

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

i This PTLR for Unit I has been prepared in accordance with the requirements of !

TS 6.9.l.II/llTS 5.6.6), Revisions to the PTLR shall be provided to the NRC after issuance. ;

The Technical Specifications addressed in this report are listed below:

i.CO 3.4 9.1 Pressure /femperature Limits; and '

LCO 3,4 9.3 Overpressure Protection Systems.

[lTS LCO 3.4.3 RCS Pressure anc' Temperature (P/T) Limits; and LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System]

2.0 Operating Limits The PTLR limits for Ilyron Unit I 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/Il IV neutron transport cross section library and ENDF/Il V dosimetiy reaction cross sections, b) Optional use of ASME Code Section XI, Appendix G, Article G 2000,1996 Addenda (not used for Ilyron Unit 1 P T curves contained in this attachment),

c) Use of ASMll Code Case N 514, and d) Use of RELAP computer code for calculation of LTOP setpoints for Ilyron Unit I replacement steam generators.

WCAP-14824, Revision 2,is included as an attachment for reference. WCAP 14824, Rev. 2 contains the Pff curves for Ilyron Unit 1, along with the weld metal data integration for !!yron and liraidwood Units I and 2 and the Byron /Braidwood fluence methodologyjustification for ENDF/ll VI cross sections.

2.1 RCS Pressure and Temperature (P/T) Limits (LCO 3.4,9.1/ [lTS LCO 3.4.3])

2,l.1 The RCS temperature rate-of change limits defined in Reference 2 are:

a. A maximum heatup of100'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

b. A maximum cooldown of 100 F in any :-hour period, and

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HYRON o UNIT I L PRESSURE AND TEMPERATURE LIMITS REPORT Operating Limits (continued)

c. A maximum temperature change ofless than or equal to 10'F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during insenice hydrostatic and leak testing operations above the heatup and !

cooldown limit curves. i 21.2 The RCS Pff limits for heatup, insenice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.1. The RCS Pff limits for cooldown are shown in Figure 2.2 and Table 2.1 These limits are defmed in WCAP.14824 Rev. 2 (Reference i 2). Consistent with the methodology described in Reference 1, the RCS Pff limits for heatup and cooldown shown in Figures 2.1 and 2.2 are provided without margins for .

Instrument error. The criticality limit curve specifies pressure temperature limits for core operation to provide additional margin during actual power production as specified in 10 .

CFR 50, Appendix G.

The P/f limits for core operation (except for low power physics testing) are that the ,

reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test, and at least 40 F higher than the minimum permissible temperature in the corresponding Pff curve for heatup and cooldown.

2.2 Low Ternperature 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 lift settings in accordance with Figure 2.3 and Table 2 2, These limits are based on References 5,13 and 14. The Residual lleat Removal (Ril) Suction Relief Valves are also analyzed to individually provide low temperature overpressure protection. This analysis for the Ril Suction Relief Valves remains valid with the current Appendix G limits contained in this PTLR document and will be reevaluated in the fbture as the Appendix G limits are ,'

revised.

The LTOP setpoints are based on Pff 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 PORY maximum lifl settings shown in Figure 2.3 and Table 2.3 account for appropriate instrument error.

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

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

(Byron Unit I 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 temperatme above 350 F).

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4 BYRON UNITI [

1+ PRESSURE AND TEMPERATURE LIMITS REPORT l Operating Lienits (continued) t T

Note that the last LTOP PORY segment in Table 2.2 extends to 450*F where the pressure setpoint is 2350 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power. -

24 Reactor Vessel lloitup Temperature (Non. Technical Specification) i i r

~

The minimum boltup temperature for the Reactor Vessel Flange shall be 2 60'F. !!oltup is a condition in which the Reactor Vessel head is installed with tension applied to any stud, ,

c'nd with the RCS vented to atmosphere (Reference 2).

2.5 Reactor Vessel Minimum Pressurization Temperature (Non Technical Specification) j The minimum temperature at which the Reactor Vessel may be pressurized (i.e., in an l 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. r i

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HYRON o UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS :

LIMITING MATERIAL: INTERMEDIATE SHELL FORGING SP 5933 (using surv capsvie data)

LIMITING ARTVALUES AT 12 EFPY: 1/4T. 70'F 3/4T, 60'F '

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Figure 2.1 Hyron Unit i Reactor Coolant System IIcatup Limitations (IIcatup Rates up to 100

'F/hr) Applicable for the First 12 EFPY (Without Margins for lustrumentation Errors) 4 !

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BYCON - UNIT I i 1

i PRESSURE AND TEMPERATURE LIMITS REPORT !

f/ ATEAIAL PAOPERTY Basts ,

LIMITING MATERIAL: INTERMEDIATE SHELL FORGING SP 5933 (u,Ing surv. capswie cata) !

LIMITING ART VALUES AT 12 EFPY: 1/47, 70'F l ydT, 60'F ;

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Figure 2.2 Hyron Ur.it 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100

F/hr) Applicable for the First 12 EFPY (Without Magins for lustrumentation Errors)

BYRON o UNIT 1 l l

PRESSURE AND TEMPERATURE LIMITS REPORT

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Table 2.1 Byron Unit 1 Heatup and Cooldown* Data Points at 12 EFPY" i (Without margins for instrumentation errors)

HEATUP CURVES COOLDOWN CURVES 1H F Healue L t to.1 Curve Critecahty LWt twg 6wady 6 tow 26 D60 F 66 D60 F 160 DEO F T I P T I P T P T i P T 4 P T { P T i P 60 0 203 0 162 2000 ~60 0 60 0 60 0 60 0 60 621 203 0 203 246te 60 621 60 695 60 554 60 470 f S 6( .]0(,[63[ ] (( [_6([~62[. [_[,.]( 3],k [6C6[ >

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Heatup and C00ldown data includes vessel flange requirements of 180 F and 621 psig per 10CFRSO, Appendix G

" For each cooldowr) rate, the steady state pressure values shall govern the temperature where no allowable pressure values are provided V

BYRON UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT i

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Figure 2.3 l Byron Unit 1 Maximum Allowable Nominal PORV Setpolnis for the Low Temperature Overpressure Protection (LTOP) System Applicable for the First 12 EFPY l

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HYRON o UNIT I l PRESSURE AND TEMPERATURE LIMITS REPORT l

Table 2.2 :

Data Points for Hyron Unit i Manimum Allowable Setpoints l for the LTOP System Appileable for the First 12 EFPY i

?

PCV 455A PCV-456 11TY 0413M) T1TY 0413P)

AUCTIONEERED 1.OW RCS PRES $UhE AUCTIONEEMED t.OW RCS PRESSURE ;

RCS TEMP. tDEG. F) IPSIG) RCS TEMP. IDEG. F) (PSIG) r 50 497 50 514 j 70 497 70 514 100 407 100 514 120 440 120 402 150 440 150 462 200 440 200 402 250 587 250 604 300 587 300 604 350 587 350 604 450 2350 450 2350 '

Note: To determine maximum allowahic lift setp9 hits for RCS Pressure and RCS Temperatures greater than 350"F, linearly interpolMe between the 350*F and 450 F data points shown above.

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HYRON o UNIT I j i

PRESSURE AND TEMPERATURE I.lMITS REPORT l

'3.0 Henctor Vessel Material Surveillance Program The reactor vessel materialirradiation surveillance specimens shall be removed and analyzed to detennine changes in material properties. The removal schedule is provided in Table 3.1. Also, !

the results of these analyses shall be used to update Figure 2.1, Figure 2.2, and Table 2.1. The l time of specimen withdrawal may be modified to coincide with those refueling outages or !

reactor rhutdowns most closely approaching the withdrawal schedule.

The pressure vessel material surveillance program (Ref. 6) is in compliance with ;

i Appendix 11 to 10 CFR 50, " Reactor Vessel Radiation Surveillance Program." The material test requirements and the acceptance standards utilize the reference nil. ductility temperature, t RTurr, which is determined in accordance with ASME, Section 111, NB 2331. ' The empirical relationship between RTun and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix 0," Protection Against Non Ductile Failure," to Section XI of the !

ASME Holler and Pressure Vessel Code. The surveillance capsule removal schedule meets the !

requirements of ASTM E185 82. ,

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1 BYRON UNIT I i PRESSURE AND TEMPERATURE LIMITS REPORT I

Table 3.1.

t i

Hyred Unit I Capsule Withdrawal Schedule [

Capsule Vessel 1 ocation Capsule Lead Removal Time"' Estimated Capsule :

(Degrees) Factor (EFPY) Fluence (rt/ cm')

t U 58.5* 3.8$ 1.15 (Removed) 3.72 x 10 ;.

-X 238.5' 3.79 5.64 (Removed) 1.39 x 10" !

i W 121.5* 3.79 8.44 (EOL Wall) 2.159 x 10"*' l 12.66(1.5 EOL Z 301.5* 3.79 Wall'") 3.238 x 10" j

.V 6).0* 3.59 Standby --- !

Y 241.0" 3.59 Standby --

l r

(a) Effective Full Power Years (ErPY) froni plant startup. !

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

(c) Derised from Tabic C 1 of WCAP 14N24, Rev. 2 (Reference 2 which is the Attachnient to this scport).

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llYRON llNIT I PRESSilRE AND TEMPERATtfRE I.lMITS REPORT 4.0 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material propenies and are provided to be consistent with Generic Letter 403. 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 vessel material properties table.

Table 4.3 provides a summary of the Byron Unit I adjusted reference temperature ( ARTS) at the 1/4T and 3/4T locations for 12 EFPY.

Table 4.4 shows the calculation of ARTS at 12 EFPY for the limiting Ilyron Unit I reactor vessel material (Intermediate Shell Forging SP-5933).

Table 4 5 provides RTns values for flyron Unit I for 32 EFPY.

Table 4.6 provides RTnsvalues for Byron Unit I for 48 EFPY.

Ii

f HYRON o UNIT I ;

I PRESSURE AND TEMPERATURE I.lMITS REPORT ,

l Table 4.1 Calculation of Chemistry Factors Using Surveillance Capsule Data f Fluence ;

Material Capsule (n/cm', FF'" Measured FF*ARTuor (FF)2 i I>l.0 ARTuor '

Mev), f inter. Shell - 5 Forging $P.5933 U 3.72x10" O.727 0 0 0529 (Tangential) .

X 1.39x 10" 1.091 30 32.73 1.190 Inter. Shell Forging SP 5933 U 3.72x10 O.727 0 0 0.529 l (Axial) !

X 1.39x10" 1.091 30 32.73 1.190 r Sum: 65.46 3.44 !

Chemistry Factor 'd' = 65.46 + 3.44 = 19.0"F llyton 1 Weld Metal WF436*' U 3.72x10" 0.727 0 0 0.00 0.529 X 1.39x 10" 1.091 35 105'" 114 56 1.190 l Ilyron 2 Weld Metal WF.447'" U 3.996x10" 0.746 0 0 0 0.557 W l .211x 10" 1.053 30 90'" 94.77 1.I10-Sum: 209.33 3.386 Chemistry Factor 'd' = 209.33+3.386= 61.8*F (a) FF = Fluence Factor = f**"*4 0 '

(b) H)ron Unit 1 ARTmrt tatues were obtained froin the suncillance Capsule X anal sis, 3 WCAP 13880 (Reference 3).

. The Dyron 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) D> ron Unit 2 capsule fluence, FF, and ARTNur values were obtained from the surveillance Capsule W analy sis (WCAP.14064) using the ENDF/U V scattering cross sectbus, (d) Chemistry Factor = %(FF'ARTun)/ %((FF)') '

(c) A(justed ARTan per Ratio Procedure of Regulatory Guide 1.99, Rey,2 (Ref,12). Ratio - 3.0, Sec Table 2 of WCAP ,

14824. Ret 2. (Ref. 2) Actual ration is 2.5 (68.0/27 0 = 2.5), however, for conservatism, ratio of 3.0 was used .;

i- 12.

t HYRON UNIT 1 ,

PRESSURE AND TEMPERATURE LIMITS REPORT I r

Table 4.2 .

i Hyron Unit i Reactor Vessel Material Properties :

Chemistry initial .

i Material Cu (%)'" Ni(%)'" Factor'd RT wt ('F)'"

Description }

Closure licad -- 0.74 .. 60'd f Flange i e

Vessel Flange .. 0,73 .. 10'd !

Inicrmediate Shell 0.0364 0.747 23.8 40 Forging SP-5933 !

Lower Shell 0.04 0.64 26,0 10 1 Forging $P-5951 I

Circumferential 0.05 0.62 68.0 30 Weld (WF.336) a) Chernistry Factors are calculated from Cu and Ni values per Regulatory Guide 1.99. Rev. 2. Position 1

(!1cf.12).

b) Initial R Tmn values are nneasured. WCAP 13880 (Ref 3) <

c) Closure head and vessel flange liutial RTmns alues are used for comidering flange requirements for the heatup/cooldoun curves in WCAP.14824. Rev 2 (Ref. 2).

+

l 13

. _ . . . .-, . --. ._._.4_ ,,n.._...._.._.,,_a.- ,2,_._.... . . _ . _ - . . _ . , . . . _,

t r

i HYRON . UNIT I PRESSURE ANI) TEMPERATURE LIMITS REPORT [

Table 4.3 !

Summary of Hyron Unit i 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 78 66 Forging SP.5933 (RG Position l'")

Using eredible 70'6' 60

surveillaisce capsule data ,

(RO Position 2'")

Lower Shell Forging 52 38 ,

SP 5951 (RG Position l'") ,

Circumferential Weld 79 43 WF 336 (RG Position l'")

Using credible 47 31 su Yeillance capsule data (RG Position 2'")

aii Calculated using a chemistry factor based on Regulatory Guide (RO) 1.99, Resision 2 Position I and 2 (Ref.12).

b) These ART values were used to generate the Upon Unit I heatup and cooldown cones in WCAP-14H24, Rev. 2 (Iter, 2).

i f-' )

f HYRON . UNIT 1 i

PHESSURE AND TEMPERATURE LIMITS REPORT 1

Table 4.4 I

Hyron Unit i Calculation of Adjusted Reference Temperatures (ARTS) -

at 12 EFPY at the Limi'.'.ig Remeter Vessel Material Intermediate Shell Forging $P-5933 (Hased on Surveillance Capsule Data)

Parameter Values Operating Time 12 EFPY Location

I/4T ART 3/4T ART

_ Chemistry Factor, CF (*F) 19.0 10.0 2

Fluence (f), n/cm 4.86x10 l .75x 10

l (E>l.0 Mev))'d Fluence Factor, FF 0.799 0 538 ARTmn= CFxFF( F) 15.2 10.2 i

Initial RT mn.,1(*F) 40 40 Margin, M(*F) 15.2 10.2 ART = 1+(CF* FF)+ M, 'F 70 60 per RG l.99, Revision 2 n) 1 luence, f, is based upon f.,,(E>l.0 Mev) = H.10x10'" at 12 EFPY (WCAP.

14824, iter 2).

b) The thron Unit I reactor vessel wall thickn:ss is H.5 inches at the beltline region.

15 -

P HYRON . UNIT I i PRESSURE AND TEMPERATURE I.lMITS REPORT l i

Table 4.5 !

RTm Values for Hyron Unit i for 32 EFPY j CF p., ppi M RTamtn ARTris RTras l Material ('F) ('F) _ (*F) (*F) ,_ _('F) intermediale Shell Forging 23.8 2.159 1.209 28.8 40 28.8 97.6 i

s SP 5933 Using Surveillance 19.1 2.159 1.209 17.0 40 23.1 80.1 :

Capsule Data'" - __

i Lower Shell Forging 26.0 2.159 1.209 31.4 10 31.4 72.8 ,

SP 5951 :

Weld Metal, WF 336 68.0 2.159 1.209 56 0 30 l 82.2 108.2 Using Surveillance 61.8 2 159 1.209 28.0 -30 74.7 72.7 Capsule Data'"

(a) 2.159 x 10" Wem'(E>l.0 Mev) for 32 EFPY flom 13yron i PTS teytt, WCAP 13881 (iter. 9).

(b) IT (11uencc Factor) = (""""'

(c) Calculated using a CF based on sunciliance capsule data per 1101,99, llevision 2. Position 2 (iter.12).

{

i l

i I

i 1

(

16 ,

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

HYRON . LINIT I j PRESSt!RE ANI) TEMPERATlfRE I lMITS REPORT !

I Tatele 4,6 i

RTns Values for Hyron linit I for 48 EFPY CF p.i ppa M RTunn ARTns RTns Material (*F) ('F) ('F) ('F) ('F) >

Intermediate Shell Forging 23 8 3.238 1.309 31.2 40 31.2 102.4 t SP.$933 Using Surveillance 19.1 3.238 1.309 17.0 40 2$.0 82.0 }

Capsule Data"'

Lower Shell Forging 20.0 = 1.238 1.309 34.0 10 34.0 78.0 ;

$P.5951 I Weld Metal, WF.336 68.0 3.238 1.309 $0.0 30 89.0 115.0 I

- Using Surveillance 61.;< .i.238 1.309 28.0 30 50.9 78.9

- Capsule Data"'

a) 2.lS9xHi" tvcin'(I>l.0 Mcv) for 32 EFPY from 11 ron l PTS repost WCAP.13881 (Ref. 9). Tlic following I 3

calculation provides flic 4M EFPY fluence value:

2.159510" + ((2.159s10" 4Hn7 A104)/32 $ 64 EITY)) * (48 32 EFPY) = 3,23Hs10* tvcm' [

b) IT (Fluence Factor) = f"'"* "5 0 c) Calculated using n CF based on suncillance capw.le data per RG l.99, Revision 2 Position 2 (Ref.12) t 4

?

t j

t 17

+"W'

HYRON . UNIT I i PRESSURE AND TEMPERATURE LIMITS REPORT 5,0 References

1. WCAP.14040.NP.A Revision 2. " Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS 11eatup and Cooldown Limit Curves", J.D. Andrachek, et. al., January 1996.

l

2. WCAP.14824, Revision 2," Byron Unit i Ileatup and Cooldown Limit Cunes 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.13880," Analysis of Capsule X from the Commonweahh Edison Company Byron Unit 1 ,

Reactor Vessel Radiation Surveillance Program", P.A. Peter, et. al., January 1994.

I

4. WCAP 12685," Analysis of Capsule U from the Commonwealth Edison Company Byron Unit 1 Reactor Vessel Radiation Suneillance Program", E. Terek, et. al., August 1990. ;

5, Westinghouse i.etter 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.

6. WCAP.9517," Commonwealth Edison Company, Byron Station Unit i Reactor Yessel Surveillance Program", J.A. Davidson, July 1979.

7. Westinghouse Letter Report to Commonwealth Edison Company, FDRT/SPRO-009(94)," Byron Unit i Ileatup and Cooldown Limit Curves for Normal Operation", P.A. Peter, January 1994.

8. WCAP.14044," Westinghouse Surveillance Capsulo Neutron Fluence Reevaluation", E.P. .

Lippencott, April 1994.

9. WCAP.13881, " Evaluation of Pressurized Thermal Shock for Byron Unit 1", P.A. Peter, January 1994.

10.10 CFR Part 50, Apnendix G. " Fracture Toughness Requirements", Federal Register, Volume 60, No,243, dated December 19,1995.

11.10 CFR 50.61," Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events", May 15,1991. (PTS Rule) .

t 12, Regulatory Guide 1.99, Revision 2," Radiation Embrittlement of Reactor Vessel Materials", U.S.

Nuclear Regulatory Commission, May 1988,

13. Comed Calculation BRW.96 9061/ LWR 96 293, Rev. 0 " Channel Accuracy for Power Operated Relief Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit i Original

- Steam Generators and Replacement Steam Generators)".

-18 <

BYCON LINIT I l PRESSURE AND TEMPERATURE LIMITS REPORT l 5.0 Rderences(continued)

14. Comed Nuclear Fuel Services Department NDIT No. 960186, Revision i " Maximum Allowable f I. TOPS PORV Setpoints for 13yron Unit I with RSGs".' l l

15. Westinghouse Letter to Comed, CAE.97 211/CCE.97 290,"flyron and 13raidwood Units 1 and 2 ATmetal Evaluation," November 7,1997.

t

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1 19'

i I

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r ATTACilMENT I

WCAP-14824, REVISION 2 HYRON UNIT I IIEATUP AND COOLDOb'N LIMIT CURVES FOR NORM AL OPERATION AND SURVEILLANCE WELD METAL INTEGRATION FOR HYRON AND HRAIDWOOD i

1

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ML20198J506

Text

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