ML20126B235
| ML20126B235 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/14/1992 |
| From: | William Cahill, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-92601, NUDOCS 9212220019 | |
| Download: ML20126B235 (8) | |
Text
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e 4
l Log # TXX-92601 File # 10010 2
903.8 (clo) 3 3
918 (clo)
Ref. # 10CFR50.34(b)
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December 14, 1992 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-446 AND 50-446 ADVANCE FSAR SUBMITTAL, FSAR SECTION 3.8.
LOADINGS AND STRESSES IN CATEGORY I STRUCTURES Gentlemen:
The attachment to this letter provides an advance CPSES FSAR submittal to facilitate NRC Staff review of the subject area in support of licensing s
Unit 2.
The attachment is organized as follows:
1.
A description / justification of each change.
2.
A copy of the revised FSAR pages (changes are indicated in the margin by a revision bar and '87").
The attached material will be incorporated in CPSES FSAR Amendment 87 which is currently scheduled for December,1992.
If you have any questions regarding this submittal, please contact Mr. Carl Corbin at (214) 812-8859.
Sincerely, William J. Cahill, Jr.
By:
M D. R. Woodlan Docket Licensing Manager CBC Attachment c.-
Mr. J.
L. Milhoan, Region IV Resident Inspectors, CPSES (2)
Mr. T. A. Bergman, NRR Mr. B. E. Holian. NRR
'l D t'. n.o 9212220019 921214 PDR-ADOCK 05000445 A
8 P
PDR 400 N. OHve Street LB 81 DaHas. Texas 75201
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CPSES - FINAL SAFETY ANALYSIS REPORT (FSAR)
AMENDHENT / REVISION 87
(; -
Attachment to TXX-92601 DETAILED DESCRIPTION Page 1 Page'1 0F 7 Prefix Page (11 amended)
Group Description 4
3.8-121 2
Clarifies the discussion (3.8.4.3.3(2)) of allowable increase in local strength capacities.
Clarification l
This change is consistent with a similar change 4
submitted for Section 3.8.4.3.2(2) in FSAR Amendment 68.
For load combination 2.b.2) of Section 3.8.4.3.3.
j local stresses caused by concentrated load Wt (design tornado load) may exceed the allowables when there is no loss of function of any safety related system.
This change is consistent with the wording in the l
Standard Review Plan (NUREG 0800).
Change Request Number
- SA-92-825.1 i
~
Commitment Register' Number :
Related SER : 3.8.3 SSER :
SER/SSER Impact
- No Table 3.8-1 2
See Sheet No(s) :1, 2, 3 and 4 Corrects the summary-of loading combinations and stresses at key locations in the Category I Structures (Table 3.8-1. " Summary Table for Category
- I' Structures").
Correction The table is revised to correct typographic errors and an error in calculating the allowable and actual' l
stresses in Unit 1.
The table is also updated with Unit 2 information. The changes have no impact on available margins of existing structures.
i Change Request Number _
- SA-92-825.2 Commitment Register Number :
Related SER : 3.8 SSER :23 3.8.3
{
SER/SSER Impact
- No i
0&R 130-45 2
Updates response to discuss the changes in design criteria of Unit 2 in contrast with the criteria of Unit 1
. Adds-note to the response of 0130.34 indicating that the response will not be incorporated i
into the FSAR text as part of the updated FSAR (USAR).
Q&R Incorporation :
l There is no change in~ design criteria between Unit 1 j
and Unit 2.
The design criteria for Units 1 and 2 is contained in the Section 3.8 of the FSAR text.
The I
editorial note is added to prepare the Q&R section for-deletion when the USAR is prepared.
Change Request Number
- SA-92-825.3 Commitment Register Number :
Related SER : 3.8 SSER :
SER/SSER Impact
- No i
i I
Attachment to TXX-92601 CPSES/FSAR Pags ? 0F 7 4)
.90 Y = 0 + L + Ta + Rn + 1.25 Pa
+1.0(Yj+Yr+Ym)+1.25Feqo 5)
.90 Y = 0 + L + Ta + Ra + 1.0 Pa
+ 1.0 (Yj + Yr + Ym) + 1.0 Fegs In these combinations, thermal loads are neglected when they are secondary end self-limiting in nature and when the material is ductile.
IncombinationsshowninItems2.a.3),4),and5),andinItems 2.b.3), 4), and 5) the maximum values of Pa Ta, Ra, Yj, Yr, and Ym, including an appropriate dynamic factor, are used, unless a time history analysis is performed to justify otherwise. For combinations 87 shown in Items 2.b.2), 4), and 5), local stresses caused by concentrated loads Yr, Yj, Ym, and Wt may exceed the allowables when there is no loss of function of any safety-related system.
Furthermore, in computing the required section strength, the plastic section modulus of steel shapes is used.
3.8.4.3.4 Variable Loads For loads which may vary, the values (within the possible range) which produce the most critical combination of loading are used in design.
3.8.4.3.5 Time Dependent Loads Time dependent loads, such as the effects of creep, shrinkage, and other related effects, are included with dead load effects, as described in Section 9.3.7 of ACI 318-71 building code, where such loads affect design.
3.8-121 Amendment 87 December 18, 1992
CPSES/FSAR t
TABLE 3.8-1 N
f (Sheet 1 of 4)
,3 d
i
'SUPMARY TABLE FOR CATEGORY 'I' STRUCTURES f
TYPE' TYPE ACTUAL ALLOW l
0F CRITICAL OF STRESS STRESS h
STRUCTURE KEY LOCATIM S (4)
LOADING C(NBINATION STRESS (KSI)
(KS1) l87 $
f i
S t
CONTAIMMENT Bottom of. Containment D+L+1.25 Pa+To+Ta+1.25E+
Tension 49.3 54.0 i
i BLDG.
Wall 9 EL.805'-6" Ra+Yr+Yj+Ya Shear 13.6 50.0(2) t
. Top of Containment 0+L+1.25 Pa+To+Ta+1.25E+
Tension 54.0 54.0 l
1-Wall 9 EL.1000'-6" Ra+Yr+Yj+Ya Inside Face of Equipment D+L+1.5 Pa+To+Ta+Ra Tension 54.0 54.0 Hatch at = 2250 for 87 l
Unit 1, 3150 for Unit 2 87 l
l REACTOR Steam Generator Compartment 0+L+Ta+Ra+Pa+(Yr+Yj+Ym)+
Axial Tension 54.0 54.0 f
BLDG.
- 1. West Cavity Wall EL 863' Feqs and Flexure Transverse 0.087 0.101(3) l Shear
{
4
?
t i
l Steam Generator Upper Lateral D+L+Ta+Ra+Pa+(Yr+Yj+Ym)+
Axial 20.6 45.0 I
Support Beam (Struct. Stl.)
Feqs Compression &
(
I Flexure Shear 6.72 20.0 87 L
Amendment 87 l
I j_
December 18, 1992 1
i:
t
CPSES/FSAR
- yg i
TABLE 3.8-1
%{
f j
l (Sheet 2)
']
- ^
l i
1 SupMARY TABLE FOR CATEGORY
'I' STRUCTURES E
f TYPE TYPE ACTUAL ALLOW 0F' CRITICAL OF STRESS STRESS g
f f
STRUCTURE KEY LOCATI(31 LOADING C0peINATION STRESS (KS1)
(KS1) l l
1
' AUXILIARY 5-A Wall East of F-A Above 0.75[1.40+1.7L+1.9Feqo+
Flexure 54 54 t'7 BLDG.
EL 790'-6" 1.7To+1.7Ro]
Shear (l) 25.5 51 87 FUEL BLDG.
C-F Wall Above EL 860'-0" D+L+To+Ro+Wt Flexure 37.8 54 l 87 i
South of col. Line 1-F Shear (l) 37.2 51 Bottom of A-F Wall Between 0.75[1.4D+1.7L+1.9Feqo+-
Flexure 35.1 54 l
4-F and 2-F 1.7 To (W)]
j D+L+To(W)+Ww Shear
.047
.103(3) i SAFEGUARDS 4-S Wall Below EL S10'-6" 0.75[1.4D+1.7t+1.9Fego+
Flexure 48.6(U1) 54 87 l
BLDG.
for Unit 1, 13-S Wall 1.7To+1.7Ro]
38.9(U2) 87
[
[
Below EL R10'-6" for Unit 2 Shear (l) 20.6(U1) 51 87 l-29.2(U2) 87
~
8-S Wall EL 810'-6" 0.75[1.40+1.7L+1.9Feqo+
Flexure 54 (U1) 54 87 i
for Unit 1, 9-S Wall 1.7To + 1.7Ro]
44.3(U2) 87
{
Be' w EL 773'-0" and 1.4D+1.7L+1.9 Feqo Shear (I) 39.0(U1) 51 87 l
l 790'-6" for Unit 2 41.8(U2) 87 i
1 i
r Amendment 87 i
)
I December 18, 1992 i
CPSES/FSAR yR TABLE 3.8-1 Ek (Sheet 3) i?
SupMARY TABLE FOR CATEGORY 'I' STRUCTURES
=
x TYPE TYPE ACTUAL ALLOW k
0F CRITICAL OF STRESS STRESS STRUCTURE KEY LOCATIONS LOADING COMBIMATION STRESS (KS1)
(KSi) i SERVICE WATER Bottom of North Exterior Wall 1.4D+1.7L+1.9Feqo Flexure 53.2 54.0 INTAKE EL.7f5'-0" STRUCTURE
" Bottom of West Exterior Wall 53.7 EL 755'-0" REFUELING Base of the Circumferential 1.4D+1.7L+1.7+ Hydro +
Flexure 52.4 54 77 WATER STOR.
Exterior Wall 1.9Fego Shear
.122
.126(3) 78 77 TANKS &.
77 CONDENSATE 77 STOR. TANKS-Amendment 87 December 18, 1992
. ~
=..
i CPSES/FSAR yR e-l l~
TABLE 3.8-1
- f, i
1
. os r i
-(Sheet 4) g l
l q%
i i
SU MARY TABLE FOR CATEGORY 'I' STRUCTURES
'3 i
d 7
TYPE TYPE ACTUAL ALLOW
- 8 i
3 Os i
0F CRITICAL OF STRESS STRESS S
STRUCTURE KEY LOCATIONS-LOADING COMBINATION STRESS (KS1)
(KSO REACTOR Base of the Circumferential 0.75[1.4D+1.7L+1.9Feqo+
Flexure 50.0 54 I 77 MAKE-UP Exterior Wall 1.7To+1.7Ro]
Shear
.068
.090(3) 87 f'
WATER 77 STOR. TANK 77 NOTES:
l77 l
.(1) Stress shown is for shear re.Aforcing steel.
77 f
i.
(2) 1" x 4" Bar Stock 87 (3) Concrete Shear Stress 77 i
(4) Unit 2 stesses are the same as Unit I s h sses except at noted.
87 t
i i
i i:
I f
4 s
r Amendment 87 1
December 18, 1992
Attachment to TXX-92601
. Pagh 7 0F 7 Q130.34 Amend the. appropriate sections of the FSAR to reflect j
the change in design criteria for Unit 2 in contrast with the criteria used for Unit 1.
]
w R130.34 There is no change in design criteria between Units 1 87 l
and 2.
i i
Note:
The above response will not be incorporated into the 87 FSAR text as part of the Q&R relocation for the Updated SafetyAnalysisReport(USAR).
l i
a i
130-45 Amendment 87 December 18, 1992-
- - _,. _ - -