ML20042E713

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Proposed Tech Specs,Consisting of Revised Reactor Vessel Toughness Tables
ML20042E713
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/25/1990
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20042E712 List:
References
0912T, 912T, NUDOCS 9005010225
Download: ML20042E713 (7)


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4 PROPOSED CHANGES:

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Copy of the current' Technical Specifications, marked-up to..

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Cu Ni P

TNUT 50 FT-LB/35 MIL RTNDT-TRANS(0)

COMPONENT HEAT NO.

MATERIAL TIPE fi),

Ill (7.)

(*F)

TEMP (a)(*F)

(*F)

USE (FT-12)

Closure Head Dome B9094-2 A3338, OL.1

.14

.55

.012 20 90 30-77

-Closure Head Segment C5086-1

.09

.54

.014 10 32 10 103 6

Closure Head Segment B8793-3

.09

.52

.012 10 53 10 96 Closure Head Flange 123W323 A508, CL.2

.69

.010 55(a) 26 55 96 V;ssel Flange 123V236

.06

.68

.004 7(a)

-2 7

131 Inlet Nozzle ZT3600-1

.12

.68

.009 60(a) 27 60 79 Inlet Nozzle ZT3600-2

.11

.67

.009 60(a) 41 60 82 Inlet Nozzle 2T3592-1

.10

.66

.011 60(a) 103 60 77 Inlet Nozzle ZT3592-2

.11

.67

.010 60(a) 51 60 82

.11

.68

.010 60(a) 60 60 86 Outlet Nozzle ZT3592-3 Outlet Nozzle ZT3592-4

.11

.68

.009 46(a) 16 46 85 Outlet Nozzle 2T3600-3

.10

.67

.011 60(a) 52 60 82 Outlet Nozzle ZT3600-4

.11

.68

.011 60(a) 46 60

>63 Upper Nozzle Shell 123V426

.06

.75

.005 10 43 10 115 Lower Nozzle Sheel ZV3300

.06

.83

.008 20 72 20 87 Inter. Shell C3795-2 A5338, CL.1

.12

.49

.010

-10 70 10 85 Inter. Shell B7835-1

.12 49

.010

-20 65 (Actual) 5 115 (Actual)

Lower Shell B7823-1

.13 48

.013

-20 56 (Actual)

-4 115.5 (Actual)

Lower Shell CIr ra-2

.15

.50

.010

-20 80 (Actsal)'

20 116 (Actual)

Bottom Head Trans.

ZV3;79 A508, CL.2

.09

.71

.010

'10 60 10 92 Ring Bottom Head Dome B7777-1 A3338, CL.1

.62

.015

-30 33

-27'

.84 Inter. to Lower Shell WF70(b)

SAW

.32

.56

.017 0(a) 0 Girth Weld Seam Inter. Shell Long.

WF4(C)

SAW

.29

.55

.013 0(a) 0 Weld Seam Inter. Shell Long.

WF8(d)

SAW

.29

.55

.013 0(a) 0 Weld Seam Lower Shell Lorg.

WF8(d)

SAW

.29

. 55

.013 0(a) 0 Weld-Seam Nozzle to Inter. Shell WF154(e)

SAW

.31

~.59

.013 0(a) 0 Girth Weld Seam SA1769(f)'

SAW

.26

.60

.019 O(a) 0 (c) Estimated using Methods of U.S.NRC NUREG-0800, Branch Technical Position MTEB 5-2, July, 1981 (b) Weld Wire Heat No. 72105 and Linde 80 Flux Lot No. 8669 (c). Weld Wire Heat No. 8T1762 e.nd Linde.80 Flux Lot No. 8597 (d) Weld Wire Heat No. 8T1762 and Linde 80 Flux Lot No. 8632 (c)' Weld _ Wire Heat No. 406L44 and Linde 80 Flux Lot No. 8720 (f) Weld Wire Heat No.'71249 and'Linde 80 Flux Lot N.'8738-o ZION UNIT 1 REACTOR VESSEL TOUCHNESS DATA-'

IABLE 3.3.2-1 0912T 88 TSC 90-03

Cu Ni P

INDT 50 FT-LE/35 MIL RINDT TRANS(G)

COMPONENT HEAT NO.

MATERIAL TYPE Q

M Ud_

(*F)

TEMP (a)(.7)

_(.El USE (FT-12)

Closure Head Dome B9094-1_

A5338, CL 1

.14

.55'

.012

-20 71 11-72 Closure Head Segment C4787-1A

.13

.62

.008 0

30 0

88 Closure Head Segment C5086-2

.09

.54

.014 30 45

-30 80 Closure Head Flange 124W609 A508, CL.2 08

.70

.010 12(a)

-13 12 105 Vcssel Flange 2V-965

.12

.74

.010 60(a) 33 60 79 Islet Nozzle ZT4007-2

.11

.70

.009 48(a) 32 46

>78 Inlet Nozzle ZT3885-1

.11

.58

.012 60(a}

43 60 S2 Inlet Nozzle ZT3885

.11

.56

.011 43(al 31 43 78 Inlet' Nozzle ZT3885

.11

.56

.012 60(a) 48 60

>84 Outlet Nozzle ZV3930

.12

.66

.010 58(a) 20 58 93 Outlet Nozzle ZV3930

.11

.65

.011 48(a) 15 48

>80 Outlet Nozzle ZV3930

.12

.67

.011 55(a) 28 55 84 Outlet Nozzle ZT3885-4

.11

.57

.013 60(a) 41 60

>61 Upper Nozzle Shell ZD3940 A508, CL.2

.07

.62

.008 10 65 10 106 Lower Nozzle Sheel ZV3855

.09

.66

.008 10

'70 10

>80 Lower Shell B8029-1 A3338, CL.1

.12

.51

.010

-10 82 22 81 Lower Shell C4007-1

.12

.53

.010 10 82 (Actual) 22 94 (Actual)

Inter. Shell B8006-1

.12

.54-

.010 10 68 10 89' Inter. Shell B8040-1

.14

.52

.008 62 2

92

' Bottom Head Trans.

3V-433 A508, CL.2

.09

.76

.010 0-43 0

87 Ring Bottom Head Dome C4007-2 A5338, CL.1

.12-

.53

.010

-20 60 0

72 Inter. to Lower Shell SA1769(b)

SAW

.26

.60

.019 0(a)

.o Girth Weld Seam l Lower Shell Long.

WF29(c)

SAW

.23

.63

.019 0(a) 0 Weld Seam

~

'l Inter. ' Shell Long.

WF70(d)

SAW

.32

.56

.017 0(a) 0 Weld Seam Nozzle to Inter. Shell WF200(8)

SAW

.24

.63

.010 0(a) 0

~ Girth Weld Seam (a) Estimated using Methods of U.S.NRC NUREG-0800, Branch Technical Position MTEB 5-2, July, 1981 (b) Weld Wire Heat'No. 71249.and Linde 80 Flux Lot No. 8738 (c) Weld Wire Heat No.'72102 and Linde 80 Flux Lot No. 8650 (d) Weld Wire Heat No. 72105 and Linde'80 Flux Lot No. 8669 l (e) Weld Wire Heat No. 821T44 and Linde 80 Flux Lot No. 8773 ZION UNIT 2 REACTOR VESSEL TOUGHNESS DATA TABLE 3.3.2-2 0912T 89 TSC 90-03

l ATTACHMENT 3 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards considerations if operation of the facility in accordance with the proposed amendment would nott 1.

Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.

Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.

Involve a significant reduction in a margin of safety.

The proposed change does not result in a significant increase in the probability or consequences of accidents previously evaluated.

Commonwealth Edison Sas conducted an extensive review of the documentation related to the integrity of the Zion Station's Unit 1 and 2 Reactor Vessels. These reviews included the following documents; Reactor Vessel Surveillance Capsules, Heatup and Cooldown Curves, Neutron Fluence Analysis, Reactor Vessel Pressurized Thermal Shock, Fracture Mechanics Analysis, and the Final Safety Analysis Report. The results of these reviews concluded that the most limiting weld neutron fluence has remained unchanged.

For both Reactor Vessels, the most limiting weld is WF 70.

This weld has been used in all appropriate calculations. As such, this change is considered to be administrative since it is merely correcting three errors of omission and a transposition error that has been shown to have no impact on plant operation or safety.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change is correcting errors that existed due to a document inconsistency.

This omission does not alter plant configuration, or operating practices.

The most limiting weld has been used in all necessary calculation. These changes are being made to correct administrative errors.

As such the possibility for a new or different type of accident is not being introduced.

The proposed change does not involve a significant reduction in a margin of safety. Based on the document review conducted, it has been concluded that the margin of safety will remain unchanged.

This conclusion is based on the fact that the limiting weld location used in the calculation of operational limitations, such as the Heatup and Cooldown Curves and Pressurized Thermal Shock, has remained the same.

0912T:5

2,.--

t' ATTACl! MENT 4 ENVIRONMENTAL ASSESSMENT STATEMENT

' Zion Station has evaluated the proposed amendment against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR51.21.

It has been determined that the proposed change meets the criteria for a' categorical exclusion as provided for under 10'CFR51.21(c)(9).- This determination is based on the fact that this change is correcting theLreference to material used in-the Unit 1 and 2 Reactor Vessels. The amendment does not involve any significant hazards considerations. There is no change in the amount or type of releases made offsite. There is no increase in individual or cumulative occupational.

radiation exposure.

0912T:6