ML18219D850
| ML18219D850 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/23/1977 |
| From: | Tillinghast J Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18219D850 (67) | |
Text
DISTRIBUTION AFTER ISSUANCE OF OPERATING LICENSE U.S. NUCI.EAR REGUl ATORY COMMIS OoglC NUMBE NRC FoRM'195 I2-76) I F NUMSEA NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO: FROM: OATE OF OOCUMENT Mr. Edson G. Case Indiana 5 Michigan Power Co.
11 23 77 New York, N. Y. 10004 OATS RECEIVEO John Tillinghast 11 25 77 I a&GETTER CINOTORIZEO PROP INPUT FORM NUMBER OF COPIES RECEIVEO
~ rR OA IG INAI ~CI.ASSIF IEO I
ClcoPY DESCRIPTION ENCI OSUAE Consists of detailed informati on the steam generator and reactor coolant pump support materials and evaluation of the fracture toughness and potential for lamellar tearing of support materials. ~ .w/att mill certifications an support drawings 2p 43p + 11/4u COOK UNITS 1 & 2 PLAh~ NAME.
jcm 12/23/77 20 SAFETY FOR ACTION/INFORMATION BRANCH CHIEF: 7 V(
INTERNAL D IST RI BUTION G F CO l'CGOU alAs EXTERN L DISTRIBUTION CONTROL NUMBER PDR:
IC SIC 773570136 CRS l CYS SENT CATE
4 QKQÃ7 INGLE'L~ Ll)Pl INDIANA 5 MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 er~I'3,~ 19 Donald C. Cook Nuclear Plant Unit Nos.
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1 Docket Nos. 50-315 6 50-316 l~) <
DPR No. 58 and CPPR No. 61 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washing ton, D.C. 20555
Dear Mr. Case:
Mr. Don K. Davis, Acting Chief of Operating Reactors Branch 42, in his September 14, 1977 letter to us, requested
,that we supply detailed information on the steam generator and reactor coolant pump support materials and our own evaluation of the fracture toughness and potential for lamellar tearing of the support materials. Attachment X is our response to the above request. Specifications for detailing, fabrication and delivery of equipment supports are given in Attachment XX. Attachment XII and Attachment XV present mill cex'tifications and support drawings respectively, Please note that ASTM-A572-70a material was not used in the fabrication of the steam generator and xeactor coolant pump supports. The materials used were ASTM-A36, and A588.
We xequired the use of A-588 material for more critical members.
A-588 requires fine grain practice,,for improved toughness.
Impact. tests of both A-36 and A-588 were specified to assure that, good toughness was obtained.
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Nr. Case , ovember 23, 1977 Page 2 Based on the through thickness mechanical tests that were required by our specification, the material would have a low propensity to lamellar tearing. Xf any cracks developed due to welding stress during fabrication, these materials with their good toughness would have a low probability that cracks would propagate. As can be seen from the Attachments, we have adequately designed and used material that will not be subject to lamellar tearing.
Very truly yours, n x, 1 nghas JT:mg Sworn and subscribed to before me on this day of November 1977 in New York County, New York Notary Public cc: R C. Callen G Charnoff P. W. Steketee R J. Vollen R. Walsh R. W. Jurgensen D V. Shaller Bridgman
l 0
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Table of Contents Page Response to Question l. ~ ~ ~ 2 Response to Question 2. 3 Response to Question 3. .38 Response to Question 4. 39 Response to Question 5. 40 Response to Question 6. 41 Response to Question 7. 42 Evaluation of Support Nate rials 43
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Question l:
Provide engineering drawings of the steam generator and the reactor coolant pump supports sufficient to show the geometry of all principal elements. Provide a listing of materials of construction.
Answer:
Attachment IV is ',a set. of engineering drawings of the D.C. Cook NSSS. The materials used in constructi on are shown with numbers on these drawings. These numbers are identified as per the ASTM specification number, yield point, material thickness group, and the testing required and are summarized in Table M9-1 of attachment II.
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QUESTION 2:
Specify the detailed design loads used in the analysis of the supports. For each loading condition (nor-and'esign mal, upset, emergency and faulted), provide the calculated maximum stress in each principal elements of the support system and the corresponding allowable stresses.
ANSWER:
The detailed design loads as provided by Westinghouse for the steam generator in report SD104 are given in the first 13 tables.
Member stress levels ex ressed as a percenta e of the allowable s ress or e upper and lower suppor s are prove e xn a es an Figures an are prove. e o x en a-men s of the steam generator supports. The loads for the Reactor Coolant pump supports are provided in tables 16 through 26.
Tables 18 through 26 include both the loads and the margin of safety under the faulted condition for the R.C. Pump supports.
Figure 3 is provided to identify the members. Stress levels for the R.C. Pump supports for the load cases normal, upset and emergency are provided in Table 27. Figure 3 identifies the elements for Table 27. The allowable stresses for each load condition and a description of the loading conditions themselves are provided in the following paragraphs.
Normal Condition Thermal, weight, and pressure forces obtained from the RCL analysis acting on the support structures are combined algebra-ically. The combined load component vector is multiplied by member influence coefficient matrices to obtain all force com-ponents at each end of each member. The interaction equations of. AISC-69 are used with allowable specified limits.
U set Condition OBE support forces are assigned all possible sign combinations and, in each case, are added algebraically to normal condition forces. The interaction and stress equations of AISC-69 are used with allowable specified limits.
Emergency Condition DBE loads are assigned all possible sign combinations, combined with normal loads, and are used in the above stress and inter-action equations. For this loading condition, limiting values of 1.5 times allowables are used. This limit represents a stress of about, 0.9 yield and provides a margin against buckling from 10 percent for short stocky members whose buckling mode is highly inelastic to a margin of 30 percent for members that buckle elastically.
Faulted Condition LOCA support structure loads are obtained in time-history form and are combined with emergency condition loads. Stress and interaction equations are solved for each time step within the time-history ..
The interaction equations of AISC-69 are adjusted such that stresses "in the support are limited to yield with the exception of the reactor coolant pump supports. Pump support members subjected 'to both compressive and tensile loads are controlled by deflection criteria associated with member failure.
The LOCA (loss of coolant accident) breaks referenced in the following tables are define'd as follows:
- DEC LOCA at the steam-generator inlet nozzle.
- h. Sl SEL LOCA at center of steam-generator outlet elbow (forces toward RV)
- i. S2 Same as h, except force away from RV.
ji UC - Unbroken loop time-history dynamic analysis due to DEC LOCA in cold leg.
- k. SL Steam-'line break DE. Note that the steam-line break is not truly a LOCA; however, was run to determine its effect on the RCL it and because it is the controlling load for the SG upper support.
Nhere a double ended circumferential break is abbreviated DEC and a single ended longitudinal is abbreviated 'SEL.
In all cases the faulted condition controls the design. The maximum stress level found for the faulted condition for the steam generator lower lateral support was 84% of the maximum
permissible. The steam generator upper lateral support is stressed to 85.1% of the maximum permissible under the faulted condition. The reactor coolant pump supports were modeled as nonlinear elastic-plastic elements and thus the failure criterion is deflection. The maximum allowable deflection is determined from deflection criteria associated with failure and to maintain the RCL piping system within its faulted limits. The margin of safety for these supports is defined as:
margin of safety = 1 maximum deflection maximum allowable deflection The minimum margin of safety obtained in the analysis was 0.5.
W TABLE 1 PRIMARY EQUIPMENT SUPPORT STRUCTURE LOADS (THERMAL'RESSURE~ DEADNEIGHT~ SEISMIC)
F F F M M M X X y -
z Equipment and Position (kips) (kips) (kips) (in. -kips) (in. -kips) (in. -kips)
Thermal
- Steam Generator (Lower) 11.66 0 2019'.7 Steam Generator (Upper) 0 0 0 Reactor Coolant Pump 0 -20.98 0 422.9 7812.0 Pressure
- Steam Generator (Lower) 0 24.57 990.2 -5478.0 Steam Generator (Upper) 0 0 0 0 Reactor Coolant Pump 0 >>17;28 0 3242.9 0 4884.6 Dea'dweight
- Steam Generator (Lower) 0 <<657.9 0 -1061.8 0 ,-632.8 Steam Generator .(Upper) 0 0 0 0 0 0 Reactor Coolant Pump 0 -210.8 438.3 -371.7
TABLE 1 (Continued)
PRIMARY EQUIPMENT SUPPORT STRUCTURE LOADS (THERMAL, 'PRESSURE, DEADWEIGHT, SEISMIC)
Operational Basis Earthquake (OBE)
F F M M M X Y y z (kips) (kips) (kips) (in. -kips) (in.-kips) (in.-kips)
"Steam Generator (Lower) 56.65 205.53 140.19 1050'.1 2351.3 2016.1
+Steam Generator (Upper) 236.13 3.94.'09 RCP (See Table 16)
- Steam Generator (Lower) 95.39 286.69 236.05 1797.8 3574.5 3480.7
+Steam Generator (Upper) 409.60 '0 342.63 RCP (See Table 16)
These OBE and DBE loads act in both positive and negative directions.
+These forces are applied to the steam generator upper lateral support model according to the shell-band interface cases defined in Figure 2.
- These loads are applied to node 13 of the model shown in. Figure 1'.
TABLE 2 STEAM GENERATOR BLOWDOWN UNBROKEN (HLB) ** (UH)
- LOWER GLOBAL FORCES+
Force (kips) Sec after Transient f(x) max = 33.2199 .424500 f (x) min = -50.6857 .453500 f (y) max = 645. 898 .136500 f(y) min = -606.747 .109500 f (z) max = 125.449 .453500 f (z) min = 82.2049 424500 Moment (in-k) m(x) max = 3284.21 .490000 m(x) min = -2601.65 .457500 m(y) max = 4317.14 .449500 m(y) min = -3161.66 .364500 m(z) max = 1257.57 .350000 m(z) min -6366.94 .492500
- For notation, see page 4.
+These loads are applied to node 13 of the model shown in Figure 1.
- Defines break in opposite loop hot leg.
TABLE 3 STEAM GENERATOR BLONDONN HOT LEG BREAK (HL)
LONER GLOBAL FORCES+
Force,(kips) Sec after Transient f (x) max = -'1.777105E-05* 0.
f (x) min = -1630. 48 .103500 f (y) max = 728. 984 2 450000E-02 f(y) min = -1177.12 4.850000E-02 f(z) max = 3.737491E-03 5.000000E-04 f(z) min = -857.633 8.550000E-02 Moment (in-k) m(x) max = 15391.6 .229500 m(x) min = -7337.14 .413500 m(y) max = 5083.47 .466000 m(y) min = -20132. 3 5.550000E-02 m(z) max = -5427.96 0.
m(z) min = -27208.5 3.800000E-02
- Computer notation, E + xx, used in this and following tables, means, the number preceding the E, times 10 to the power of the xx number following the E (exponent) .
+These loads are applied to node 13 of. the model shown in Figure 1.
TABLE 4 STEAM GENERATOR BLOWDONN STEAM GEN INLET (SZ)
LOWER GLOBAL FORCES+
Force (kips) Sdc after Transient f (x) max = -1. 777107E-05 0.
f (x) min = -837.034 .367000 f (y) max = 2232. 01 .491500 f(y) min = -877.222 4.550000E-02 f(z) max = 165.774 6.650000E-02 f(z) min = -539.380 .300500 Moment (in-k) m(x) max = 10800.6 .228500 m(x) min = -6183.59 .197500 m(y) max = 18284.5 .178000 m(y) min = -23408. 1 .160500 m(z) max = 4276.82 .200500 m(z) min = -15688.8 .233000
- These loads are applied to node 13 of the model shown in Figure 1.
TABLE 5 STEAM GENERATOR BLOWDOWN STEAM GEN OUTLET BREAK LOWER GLOBAL FORCES+
Force (kips) Sec after Transient, f max = 73.0130 f (x)
(x) min = -347.176 4.650000E-02 2.100000E-02 f(y) max = 2822.90 7.850000E-02 f(y) min = -1864.35 5.000000E-02 f(z) max = 859.139 2.100000E-02 f(z) min = -180.680 4.650000E-02 Moment (in-k) m(x) max = 8309.46 3.350000E-02 m(x) min = -1492.11 6.600000E-02 m(y) max = 7564.15 7.050000E-02 m(y) min = -4530.87 4.750000E-02 m(z) max = -310.483 .177000 m(z) min = -13225.8 .208000
- Supports Seismically Compensated. The "seismically com-pensated" notation accounts for the seismic load on the
'support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
+These loads are applied to node 13 of the model shown in Figure l.
11
TABLE'6 STEAM GENERATOR BLOWDOWN PUMP INLET BREAK LOWER GLOBAL FORCES*
Force (kips) Sec after Transient f (x) ma'x = 106.492 5.700000E-.02 f(x) min = -239.636 3.550000E-02 f (y) . max = 2245. 81 2.950000E-02 f (y) min = -1855.47 5.750000E-02 f(z) max = 593.022 3.550000E-02 f(z) min = -263.518 5.700000E-02 m(x) max = 4311.32 2.300000E-02 m(x) min = -2203.27 .168500 m(y) max = 28419.8 .133500 m(y) min = -18722. 0 .114500 m(z) max = 3615.46 .126000 m(z) min = -16481.7 3.600000E-02
- These loads are applied to node 13 of the model shown in Figure 1.
12
TABLE 7 STEAM GENERATOR BLOWDOWN COLD LEG BREAK (CL)
LOWER GLOBAL FORCES*
Force (kips) Sec after Transient f (x) max = 33.2430 .402000 f(x) min = -41.3760 .307000 f(y) max = 790.901 3.150000E-02 f (y) min = -675. 064 5.550000E-02 f(z) max = 102.241 .307000 f (z) min = -82.2925 .402000 Moment (in-k) m(x)'ax = 5600.41 3.800000E-02 m(x) min = -3265.61 7.100000E-02 m(y) max = 24784.6 .358500 m(y) min = -17885.5 .340500 m(z) max = 1053.12 .24SOOO m(z) min -10041. 0 .219000 H
- These loads are applied to node 13 of the'odel shown in Figure 1.
13
TABLE 8 STEAM GENERATOR BLOWDOWN (XLHR)
LOWER GLOBAL FORCES*
Force (kips) Sec after Transient f(x) max = 3.18927 4.500000E-03 f(x) min = -230.700 .132500 f(y) max = 2871.19 7.200000E-02 f (y) min -1456. 62 '.350000E-02 f(z) max = 570.911 .182500 f(z) min = -7.89392 4.500000E-03 Moment (in-k) m(x) max 4426.78 2.900000E-02 m(x) min -1463.19 5.750000E-02 m(y) max 26862.2 8.050000E-02 m(y) min -5742.71 9.750000E-02 m(z) max -2295.56 .173000
'(z) min -17477.8 .203000
- These loads are applied to node 13 of the model shown in Figure l.
14
TABLE 9 STEAM GENERATOR BLOWDOWN UNBROKEN (CLB)** (UC)
LOWER GLOBAL -FORCES*
Force (kips) Sec after Transient ff (x)
(x) max =
min =
- 41. 8566
-50.3932
.409500
.239500 f (y) max = 360'.556 .156000 f(y) min = -334.495 .3.98000 f (z) max = 124. 725 .239500 f (z) min = -103.580 .409500 Moment (in-k) m(x) max = 4626.59 .112000 m(x) min = -3708.69 .250000 m(y) max = 3463.28 .364500 m(y) min = -3291.89 .411000 m(z) max = -589. 657 .261000 m(z) min = -7249.29 .398500
/
- These loads are applied to node 13 of the model shown in Figure 1.
- Defines break in opposite loop cold leg.
15
Qj 4.
TABLE 10 STEAM GENERATOR BLOWDOWN SPLXT 1 SGOE (Sl)
LOWER GLOBAL FORCES*
1 Force (kips) Sec after Transient f (x) max = 188. 406 .000000E-02 f (x) min = .217394 500000E-03 f (y) max = 2429.24 .202500 f (y) min ~ -.2243.43 .173500 f (z) max = .538015 .500000E-03 f(z) min = -466.394 .000000E-02 Moment (in-k) m(x) max = 13003.0 500000E-02 m(x) min = -3365.22 .600000E-02 m(y) max = -2.118177E-07 m(y) m'n = -72224.7 .800000E-02 m(z) max = 12450.8 .475000 m(z) min = -16189.0 .386500 I
- These loads are applied to node 13 of the model shown in Figure 1.
'- 16
TABLE ll STEAM GENERATOR BLOWDOWN SPLIT 2 SGOE (S2)
LOWER GLOBAL FORCES*
Force (kips) 'ec after Transient f (x) max = 499. 650 .260000 f(x) min = -1.777105E-05 0.
f (y) max = 2415.47 .202500 f(y) min = -2234.61 ;3.73500 f (z) max = 147.706 1.250000E-92 f(z) min = -587.085 3.250000E-02 Moment (in-k) m(x) max = 13055. 4 3.450000E-02 m(x) min = -3302.59 .354000 m(y) max = -2.119923E-07 0.
m(y) min = -95727.2 .156500 m(z) max = 12743.3 .472500 m(z) min = -13560.9 .386500
- These loads are applied to node 13 of the model shown in Figure l.
17
TABLE 12 STEAM GENERATOR BLOWDOWN STEAM LINE BREAK (SL)
LOWER GLOBAL FORCES*
Force (kips) Sec after Transient f(x) max = 130.228 .148500 f(x) min = -605.631 .178000 f(y) max = 376.230 .477500 f(y) min = -319.381 .448000 f(z) max = 870.824 .178000 f(z) min = -298.343 .148500 Moment (in-k) m(x) max = 29915.0 .142000 m(x) min = -25678.5 .174000 m(y) max = 15962.0 .124500 m(y) min = -14346.0 .141500 m(z) max = 16852.2 ~ 450000E-02 m(z) min = -28070.8 .396000
- These loads are applied to node 13 of the model shown in Figure 1.
18
STEAM GENERATOR BLOWDOWN STEAM LINE BREAK (SL)
UPPER GLOBAL FORCES*
Force (kips) Sec after Transient f (x) max = 2025.27 4.100000E-02 f (x) min = -6. 366463E-ll 0.
f (y) max = 0. 0.
f (y) min = 0. 0.
f (z) max = 415. 060 .217500 f (z) min = -2302. 78 .252000 Moment (in-k) m(x) max = 0. 0.
m(x) min = 0. 0.
m(y) max = 0. 0.
m(y) min = 0. 0.
m(z) max = 0. 0.
m(z) min = 0. 0.
- These forces are applied to the Steam Generator upper lateral support model according to the shell-band in-terface cases defined in Figure 2.
J5 47
~ 4~D 0 4 ~
25 24 23 21 22 40 39 20 19 18 17 31 21 20 17 30 19 16 23 22 PLAII 25 IS 15 16 18 24 12 14 13 8 7 26 Z 10 45 46 37 I
27 36 8 .
33 35 9
29 31 32 30 34 32 51 53 52 10 S4 3 33 35 2 16 9 5 15 8 3 7 '4 2 12
<'7 ELEVATIOII 13 29 28 26
'b a'Oib" 'At4 d >
'ao f gg ~
Figure Steam Generator Lower Supporl Model 20
TABLE 14 STEAM GENERATOR LONER SUPPORT STRESS MAXIMUM MEMBER STRESS % MAXIMUM PERMXSSXBLE Loading Condition
+Member Normal Upset Emergency Faulted 3.2 3.7 34.2 5.3 5.9 14.8 7.7 8.9 30.7 4.6 5.1 13.6 3.4 3.8 36.4 12.1 13.4 35.8 3.5 3.8 49.6 3.4 3.7 53.8 11.8 13.0 4.5 10 8.7 9.9 64.9 .
51.4 57.9 40.0 68.1 12 9.4 19.5 16.1 65.9 13 38.2 43.7 30.1 68.4 14 2.3 7.7 6.8 69.7 15 3.3 3.5 24. 6 16 5.3 6.1 22 '
17 13.4 14.7 43.3 18 .6 6.2 19 3.3 3.6 15.5 20 7.6 8.4 22.9 21 23 ' 25.7 84.0 22 2.9 3.2 13.3
TABLE 14 (Continued) 0 STEAM GENERATOR LOWER SUPPORT STRESS MAXIMUM MEMBER STRESS % MAXIMUM PERMISSIBLE Loading Condition
+Member Normal Upset Emergency Faulted 23 6.5 7.2 19.0 24 .8 .9 14 '
25 10.2 11.1 61.- 8 26 4;0 4.5 30.2
.9 8.6 28 9.0 10.3 80.5 29 5.7 6.5 40.9 30 13.1 14.3 54.4 3.2 3.5 12.5 32 7.6 8.8 18.7 33 3.0 3.3 11.3 34 23 '. 25.5 68.2 35 6.1 6.7 44.3 36 10.8 11.9 35.6 37 1.0 1.1 6.4 38 4.0 4 4 11.5
- 39 11.4 12.6 33.8
- 40 4.8 5.3 51.1
- 51 4.3 4.7 67.5
- 52 4.3 4. 7. 67.5
- 53 5.4 5.8 75.8 5.4 5.8 75.8
- The stress levels for these elements were determined by S&L. The levels determined will envelope the actual level from the L0 analysis.
+See Figure 1 for member locations.
22
'.X h
CASE A CASE B HOTE: SHADED AREAS !HDICATE S.G. SHELL AHD BAHD IHTERFACE.
Support Case Definition Upper Steam Generator Supporr Figure. 2 Load components are combined through the principle of superposition of case A and case B.
23
, TABLE 15 TABLE 15a
.STEAM GENERATOR UPPER SUPPORT STRESSES (RING) +
OPERATING CONDITION MAXIMUM STRESS PERCENT OF (psi) PERMISSIBLE STRESS NORMAL Not applicable UPSET 4,948 16.5 (OBE) .
EMERGENCY (DBE) 8,633 19.2 FAULTED 42,578 85.1 TABLE 1'5b FAULTED CONDITION
- COMPONENTS OF PERMISSIBLE STRESS+
80.0 63.0 79.1 80.0
+All stress levels determined by S&L to envelope actual stress levels. 'I
- See Figure 2 for location of components.
30
'b 19 18
~~ 13 II 10 16 0
29 Pump
/
15
/ Y 25 12 PLAN
/ 13 Qn r l0 26 ?
30 0.4. 26 9L X 27 Secondary Shield Nail A3 4 4 0
P di 3
~ NI 13 16 12 9 26
'3 ELEYATIOM 17 26 22 21
- 3
,a; Basemat Figure 3 Reactor Coolant Pump Support Model 25
TABLE 16 PRIMARY EQUIPMENT SUPPORT STRUCTURE LOADS I
(REACTOR COOLANT PUMP SE SMIC 'LOADS ~ kips )
Operating, Basis Earthquake (OBE) Tension Compression
- Member 7 0.0 53.9 Member 8 0.0 80.0 Member 9 0.0 80.0 Member 10 0.0 57.4 Member 15 101.6 101.6 Member 16 147.3 147.3 Member 17 134.5 134.5
- See Figure 3 for member locations.
26
e TABLE 17 PRIMARY EQUIPMENT SUPPORT STRUCTURE LOADS (REACTOR COOLANT PUMP SEISMIC LOADS, kips)
Design Basis -Earthquake (DBE) Tension Compression
- Member 7 0.0 80 '
Member 8 0.0 118.8 Member 9 0.0 118.8 Member 10 0.0 85.5 Member 15 150.6 150.6 Member '16 216.7 216.7'17.2 Member 17. 217.2
- See Figure 3 for. member 1ocations 27
C 4
TABLE 18 LOADS AND DEFLECTIONS REACTOR COOLANT PUMP COLUMN 16 TENSION (a)
Without Seismic With Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 933 1048 (d)
Maximum Deflection (inches) 0.193 0.257 (e)
Permanent Plastic Deflection (inches) 0.010 0.058 Maximum Allowable Deflection (inches) (b) 3.3 3.3 Margin of Safety (c) +0.94 +0.92
- a. The loads and deflections presented in this table are for the most-severely loaded member, attached to point 16.
,They are based upon the most,-severe postulated break considered, steam-generator-outlet nozzle (SG) ) . See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. column.
S f Margin of+ Safety
~
t = 1 maximum def 1 ection maximum allowab e ef ection d.'his number includes seismic load of 217 (kips) .
- e. This number includes seismic deflection of 0.041 (inches).
- f. The "seismically compensated" notation accounts for the seismic load on the support, by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point, on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
28
TABLE .19 LOADS AND DEFLECTIONS REACTOR COOLANT PUMP COLUMN 17 TENSION (a)
Nithout Seismic Nith Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 667 884 (d)
Maximum Deflection (inches) .127 .168 (e)
Permanent Plastic Deflection (inches) none none Maximum Allowable Deflection (inches) (b) 3.3 3.3 Margin of Safety (c) +0.96 +0.95
- a. The loads and deflections presented in this table are for the most-severely loaded member, attached to point 9. They are based upon the most-severe postulated, break considered, Crossover-Leg Break (XLHR). See Figure 3.
- b. This value is based on load deflection relationship for R.C. P . column.
- c. Margin of Safety = 1 maximum deflection maximum a lowable deflection
- d. This number includes seismic load of 217 (kips).
I
- e. This numbed includes seismic deflection of 0.041 (inches).
The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
29
TABLE 20 LOADS AND DEFLECTIONS REACTOR COOLANT PUMP COLUMN 15 TENSION (a)
Without Seismic With Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 118 357 (d)
Maximum Deflection (inches) 0.011 0.067 (e)
Permanent Plastic Deflection (inches) none none Maximum Allowable Deflection (inches) (b) 3.3 3.3 Margin of Safety (c) +0.99 +0.98
- a. The loads and defle'ctions presented in this table are for the most-severely loaded member, attached to point 12.
They are based upon the most-severe postulated break con-sidered, steam-generator-outlet nozzle. See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. column.
- c. Mar in of Safet = 1 maximum deflection maximum allowable deflection
- d. This number includes seismic load of 217 (kips).
- e. This number includes seismic deflection of 0.041 (inches).
- f. The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point. on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
30
TABLE 21 LOADS AND DEFLECTIONS REACTOR COOLANT PUMP COLUMN 16 COMPRESSION (a)
Without Seismic With Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 200 423 (d)
Maximum Deflection (inches) 0 '22 0.047 (e)
Permanent Plastic Deflection (inches) none none Allowable Deflection 'aximum (inches) (b) 1.390 1.390 Margin of Safety (c) +0.98 +0.97 a~ The loads and deflections presented in this table are for the most-severely loa'ded member, attached to point 16.
They are based upon the most-severe postulated break con-sidered, steam-generator-outlet nozzle. See Figure 2.
- b. This value is based on load deflection relationship for R.C.P. lateral support.
c; Margin of Safety = 1 maximum deflection maximum allowable deflection
- d. This number includes seismic load of 217 (kips) .
- e. This number 'includes seismic deflection of 0.024 (inches).
- f. The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point, on the deflection axis is redefined as the eauivalent elastic deflection of the seismic load.
TABLE 22 LOADS AND DEFLECTIONS REACTOR COOLANT PUMP COLUMN 17 COMPRESSION (a)
Without Seismic With Seismic Identification Compensation Com P ensation ( f)
Maximum Load (kips) 600 v48 (a> I Maximum Deflection (inches) 0.067 0.084 (e)
Permanent Plastic Deflection (inches) none none Maximum Allowable Deflection
.(inches) (b) 1.390 1.390 Margin of Safety (c) +0.95= +0.94
- a. The loads and deflections presented in this table are for the most-severely loaded member, attached to point 9.
They are based upon the most-severe postulated break con-sidered, steam-generator-outlet break (SGO). See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. lateral'upport.
- c. Margin of Safety = 1 maximum deflection maximum allowable ef lect@on
- d. This number includes seismic load of 217 (kips).
- e. This number includes seismic deflection of 0;024 (inches).
The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
32
TABLE 23 REACTOR COOLANT PUMP COLUMN 15 LOADS AND'EFLECTIONS (COMPRESSION) (a)
Without Seismic With Seismic Identi'fication Compensation Compensation (f)
Maximum Load (kips) 1175 1292 (d)
Maximum Deflection (inches) 0.132 0.157 (e)
Permanent Plastic Deflection (inches) 0.001 Maximum Allowable Deflection (inches) (b) 1.'390 1.390
.Margin of Safety (c) +0.91 +0.89
- a. The loads and deflections presen'ted in this table are for the most-severely loaded member, attached to point 12.
They are based upon the most-severe postulated break con-sidered, steam-generator-outlet nozzle (SGO). See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. lateral support.
- c. Margin of Safety = 1 maximum deflection maximum allowable deflection
- d. This number includes seismic load of 217 (kips).
- e. This number includes seismic deflection of 0.024 (inches) .
The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection. curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
33
TABLE 24 LOADS AND DEFLECTZONS REACTOR COOLANT PUMP LATERAL SUPPORT (a)
Without Seismic With Seismic Xdentification Compensation Compensation ('f)
Maximum Load (kips) 722 770 (d)
Maximum Deflection (inches) 0.113 0.120 (e)
Permanent Plastic Deflection none none (inches)
Maximum Allowable Deflection (inches) (b) 0.99 0.99 Margin of Safety (c) +0.89 +0.88
- a. The loads and deflections presented in this table are for the most-severely loaded member, attached to point 16.
They are based upon the most-severe postulated break con-sidered, crossover-leg break (XLHR). See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. lateral support.
maximum -,deflection maximum allowab e deflect'.on
- d. This'number includes seismic load of 86 (kips) .
- e. This number includes seismic deflection of 0.013 (inches).
The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
'34
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TABLE 25 REACTOR COOLANT PUMP LATERAL SUPPORT LOADS AND DEFLECTIONS (a)
Without Seismic With Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 841 84> <aJ Maximum Deflection (inches) 0.279 0.354 (e)
Permanent Plastic Deflection (inches) 0.141 0.236 Maximum Allowable Deflection (inches) (b) 0.99 0.99 Margin of Safety (c) +0.72 +0.50
- a. The loads and deflections presented in'his table are for the most-severely loaded member, attached to point 9.
They are based upon the most-severe postulated break con-sidered, steam-generator-outlet nozzle (SGO) . See Figure 3.
- b. This value is based on load deflection relationship for R.C.P. lateral support.
- c. Margin of Safety = 1 maximum deflection maximum allowable de lection
- d. This number includes seismic load of 119 (kips).
- e. This number includes seismic deflection of 0.137 (inches).
The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis is redefined as the seismic load, and zero point on the deflection axis is redefined as the equivalent elastic deflection of the seismic load.
TABLE 26 LOADS AND DEFLECTXONS REACTOR COOLANT PUMP LATERAL SUPPORT (a)
Without Seismic With Seismic Identification Compensation Compensation (f)
Maximum Load (kips) 366 472 (d)
Maximum Deflection (inches) 0.057 0.074 (e)
~
Permanent Plastic Deflection (inches) none none Maximum Allowable Deflection (inches) (b) 0.99 0.99 Margin of Safety (c) +0.94 +0.93
- a. The loads and deflections presented in this table are for the most-severely loaded member, attached to point 12.
They are based upon the most-severe postulated break con-sidered, crossover-leg break (XLHR). See Figure 3.
- b. ~ This value is based on load deflection relationship for R.C.P. lateral support.
maximum deflection max>mum a lowable deflection
- d. This'number includes seismic load of 86 (k.-'.ps).
- e. This number includes seismic deflection of 0.013 (inches).
- f. The "seismically compensated" notation accounts for the seismic load on the support by shifting the axis of the load-deflection curve. The zero point on the load axis
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36
TABLE 27 REACTOR COOLANT PUMP SUPPORT STRESSES Loading Condition Member* Normal .
Upset Emergency Maximum Member Stress, 0 Maximum Permissible 11.0 10.9 6.8 6.7 4.7 4.7 6.9 6.9 6.7 6.6 4.5 4.5 7 4 4 4.4 6.6 6.5 6.6 6.5
,10 .4.7 7 11 4.8 4.8
'2 6.7 6.6 13 4.9 4.8 14 6.8 6.7 15
- 22.8 33.1 25.4 13.8 27.1 22.3 17 18.6 32.2 ,27. 1
- See Figure 3 for member locations.
37
Question 3 Describe how all heavy section intersecting weldments were designed to minimize restraintand lamellar tearing. Specify the actual section thickness in the structure and provide details of typical joint design. State the maximum design stress in the through thickness direction of plates and elements of rolled shapes.
Answer:
The D.C. Cook NSSS drawings provide both typical joint details and section thickness. The design of the heavy section intersecting weldments was made under the provisions of the 1969 AISC code. The joint details are therefore consistant with current practice in structural design. plates were tested in the through gauge thickness. Reduction of area was generally above 20 percent indicating good resistance to lamellar tearing. Calculated stress leveliin the through thickness direction is 65/o of yield. Materials that were subjected to transverse stress, classified as 3B in the drawings, were subjected to ultrasonic examination along all edges and on a specified grid in accordance with A-435. The area under all welds on through thickness extending to 3" on either side of the weld was 100% ultrasonically examined. Welding was required to be performed in accordance with AISC code and ASME (B&PV) Code Section VIII. The joints were stress relieved with post weld heat treatment in accordance with ASME code requirements. The above requirements on the heavy section intersecting weldments will minimize the possibility of lamellar tearing.
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Question 4:
Specify the minimum, operating temperature for the supports and describe the extent to which material temperatures have been measured at variouspoints.'on the supports during the operation of the plant.
Answer:
Technical specifications for Donald C. Cook Nuclear plant require that the air temperature in the region where the supports are located should be maintained between 60 F and 120~P during operation. No actual temperature measurements of the supports have been taken during operation of the plant. Both A-36 and A-588~
materials were specified to pass a Charpy V-Notch test of 15 ft-lbs.
at 30 P. Section 16.2 of the attached specification no DCC-CE-112 QCN (attachmentIX) requires that the impact test be performed in conformance with paragraph SA-310 of ASME Section II Code. The test results indicate that all critical materials were Charpy tested and met the above requirement.
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Specify all the materials used in the supports and the extent which mill certificate data aLe available. Describe any supplemental requirements such as melting practice, toughness tests and through thic'kness tests specified. Provide the results of all tests that may better define properties of the materials used.
Answer:
The materials used in the support are described I i:n Table M9-1 of Attachment. II. Mill certification reports are available for all materials used in fabrication,.
Typical mill ci rtifications are presented in attacbmentQzx.
Charpy-V Notch test were performed to determine strain rate and temperatures. Ultrasonic examinati.on was,used to detect plate laminations. Section 15.5 of LAttachment ZI requires that the ultrasonic inspection be performed subject to the mote restrictive requirements of the following two documents: (1)
Appendix U of ASME Section UIII, Division I, and (2) ASSN 164.
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Question 6 Describe the welding procedures and any special welding process requirements that were specified to minimize residual stress, weld and heat affected zone cracking and lamellar tearing of the base metal.
Answer Details of welding proce'dures are presented in Section 13.0 through 13.9 of Attachment ~XI. Table W 13-9 specifies the requirements for welding of A-558. All materials were welded based on approved welding procedures and all welders were qualified in accordance with ASME B 6 PV Code.
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Describe all inspections and non destructive tests that were performed on the supports during their fabrications and installation.
( as well as any additional inspections that, were performed during the life of the facility).
Answer Section 15 of AttachmentII describes requirements for non destructive testing of,welds. All welds were examined volumetrically by radiographic or 'bj ultrasonic methods where practical. If volumetric examination could not be performed welds were surface examined by either magnetic particle or penetrant methods. During erection, all fieldswelds were magnetic particle examined, in accordance with AWS Dl.'1-72 plus an intermediate root pass examination of welds over 3/8 " thick.
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- 8. Evaluation of the fracture toughness of the steam generator and reactor coolant um su ort materials The NSSS specification requires that A36,material, he modified to fine grade practice. This is a steelmaking'process which improves the notch toughness properties. The A588 material was purchased in the normalized condition. This guarantees ferritip fine grain size, lowers the ductile to brittle transition, temperature and improves toughness. Both A36 and A588 materials were specified to pass a Charpy V-Notch test of 15 ft. lbs. at +30" F. The operating temperature of these supports is far in excess of the specified test temperatures.
Therefore, these materials will be subject to temperatures above the transition temperature.
Question no. 6 of the NRC letter asks for a description of processes which were utilized to minimize residual stresses, weld and heat affected zone cracking and lamellar tearing of the base metal. The Cook NSSS specification specified the following welding requirements to eliminate these concerns.
- l. Welding was performed in accordance with ASME B & PV Code to assure adequate preheat and postheat temperatures.
- 2. Low hydrogen electrodes and properly dried',flux for submerged arc, welds, were specified.
The NRC's concern regarding lamellar tearing was initiated by the North"Anna Station cracking. Materials used for supports at the Donald C. Cook Nuclear Plant were ultrasonically examined and impact tested, and are, therefore, less susceptable to lamellar tearing.
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