ML19319D462
| ML19319D462 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/12/1976 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| Shared Package | |
| ML19319D457 | List: |
| References | |
| NUDOCS 8003170591 | |
| Download: ML19319D462 (5) | |
Text
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.h.
U TELECON MEMO TO:
J. T. Rodgers, Florida Power Corporation FROM:
L. B. Engle, NRC DATE:
November 12, 1976 This is not yet official, but I understand what is being transmitted to you will be official next week. I am giving it to you so you can begin to react immediately,
SUBJECT:
Material Specimen Surveillance Program for Reactor Vessel.
Surveillance Specimens for Crystal River Unit #3 The Material Ingegrity Section of the' Materials Engineering Branch Division of System Safety has evaluated the information contained in the letter dated November 5,1976, from Mr. J. T. Rodgers, Florida Power Corporation, in regard to your integrated irradiation program for the Reactor Vessel for the CR#3 Plant.
The FSAR for this plant states in Section 4. 4. 5 that the ' governing criteria for the material surveillance program is ASTM E-185-70 and that the program will meet the intent of Appendix H 10CFR, Part 50.
Insufficient information is presented in Table 1 and 2 of the subject letter for the Materials Engineering Branch to determine whether the suggested approach meets the requirements of Appendix H.
We require that all specimens in capsules be identified and their identity be related to the materials in CR#3 Reactor V_essel belt line region. Specimen location should also be identified in relation to the fracture toughness re-quirement of Appendix G,10CFR, Part 50, and Appendix G, of the ASME
~
Code.
The withdrawal schedule of the capsules in compliance with Appendix H should be related to the irradiation dosage and the anticipated shift in RT during the life of the CR#3 Reactor Vessel.
NDT Leon Engle 3:15 p. m.
11/12/76 8003170 N [
TABLEl e
Materials and Snecimens in Surveillance Capsules
~
i of Crystal River 3 Capsules CR 3-A,
-C,-E Number of Specimens Material Descrintion Tensile Charpy 1.
Weld metal, WF 209 2
12 2.
Weld-HAZ Heat C4344 transverse 0
12 Heat C4344 transverse
.0 6
3.
Base metal forgings Heat C4344 transverse 2
12 heat C4344 transverse 0
6 4.
Correlation Material 0
6 Total per capsule 4
54 Capsules CR 3-B,
-D,-F Number of Soeciner.s Material Descriction Tensile Charov 1/2 iCT 1.
Weld metal, WF-209 2
12 8
~
2.
Weld-HA2 Heat C4344 transverse 0
12 0
e 3.
Base metal Heat C43 44 transverse 2
12 0
Total per capsule 4
36 8
e e
S e
BELTLINE REGION MATERIAL DATA FOR CRYSTAL RIVER S 1
\\
QIARPY DATA, CVN W.
Drop Longitudinal Transverse 1
MATERIAL BELTLINE wt.
IDENTIFI-MATERIAL REGION TNDT ft-lbs at 10*F cv U.S.E*
RT NOTES CATION NO.
TYPE LOCATION NDT Cu P
S
- F ft-lbs
- F ft-lbs
- F 10
.054
.008
.006 lABM96 SA508 Cl-2 Nozrle Belt 20 13, 12, 11 iC4344-1 SA533B Upper Shell
-10 (0*F)39, 32, 32 80 88 20
.20
.008
.016
!C4344-2 SA533B Upper Shell
-10 (0*F)20, 33 80 88 20
.20
.008
.016 -
..C4347-1 SA5338 Lower Shell
-20 36, 42, 61
-20
.12
.013
.015 IC4347-2 SA533B Lower Shell
-20 9, 9, 24 100 119 40
.12
.013
.015 WF209-1 Weld Surveillance
-50 29, 30, 32 103 63 43
.30
.020
.005 WP 8 Weld Upper Long 45, 38, 30 (66)
(20).20
.009
.009 (100%)
q (66)
(20).105
.091
.004 h
45, 46, 38 WF 18 Weld Upper Long (100%)
t~
ta (66)
(20).106
.014
.013 m
36, 43, 42 WF '169,
Weld Upper Cire.
(60%0D)
(66)
(20)
.19
.021
.016 36, 35, 38 SA1769 Weld Upper Cire.
(40%ID)
(66)
(20)
.27
.014
.011
,WF 70 Weld Middle Cire.
39, 35, 44 (100%)
(66)
(20)
.22
.015
.013 49, 41, 40 SA1580-Weld Lower Long (100%)
WF 154 Weld Lower Cire.
41, 37, 43 (6'6)
(20).20
. 015
.021 (100%)
- Surveillance Base Metal A
(.) Lower Bound 'per BAW-10046P
- Surveillance Base Metal B
- Surveillance Weld' Metal 8
TABLE 3 REACTOR VESSEL MATERIAL IRRADIATION SCHEDULE Fraction of the Service Life Design (2)
Flu enc e,1 Fluence at Expected Shift E > 1. O Me(v)1/4t Location in RTNDT, *F Capsule Installation Removal A
End of 1st Cycle Standby 9
C End of 1st Cycle End of 9th Cycle
- 1. 28 x 10 0.76 215 E
End of 1st Cycle Standby B
Initial Fuel Load End of 1st Cycle
- 0. 29 x 10 0.17 115 9
D Initial Fuel Load End of 5th Cycle
- 0. 93 x 10 0.55 190 9
F End of 1st Cycle End of 5th Cycle
- 0. 64 x 10 0.38 160 i
NOTES:
19 (1) The design life fluence is 1. 68 x 10
, E > 1 Mev at the 1/4t location, e
1 and the fluence per cycle for capsules B and D is 0.29 x 10 9 for the first cycle, and is 0.16 x 10 9 for subsequent cycles for capsules C, 1
D and F.
(2) Based on proposed Regulatory Guide 1. 99, Figure 1.
/
o U)MPONENT llT. MO.
o Nozzl.c Belt 123Vi90
[
~
~
(AEM 96)
Upper Shell C4344-1 g
C4344-2 Lower Shell C4347-1
(-
C4347-2 Dutchman 124W295VA1 f
\\;
)
i
~
T 169 (607,) oo 3
A 1769 (407,)10 MF8Cteds)*
.e-.WFl%q,}
~
9 0 D W m1 g gij 6
j
-C WF 70 (1007) m
~
M co SA1580 (1 ]O7.)j
~.
w a 1l WF 154'(1007.)'
^
{
FIGURE 1 -
Identification of CR3' Reactor Vessel.Seltline Materials.
4 l
.-