ML19283B586
| ML19283B586 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/14/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LAC-6118, NUDOCS 7902260446 | |
| Download: ML19283B586 (10) | |
Text
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EMIRYLAND POWER COOPERATIVE Ea Crosse, OYisconsin
$4601 February 14, 1979 In reply, please refer to LAC-6118 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE EOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERA'fING LICENSE NO. DPR-45 PROPOSED MODIFICATION - SPENT FUEL STORAGE
Reference:
(1)
DPC Letter, LAC-6015, Linder tc Director of Nuclear Reactor Regulation, dated November 29, 1978.
Gentlemen:
Enclosed with this letter is additional information concerning the seismic analysis of the LACBETR spent fuel storage pool drain line submitted to you by Reference (1).
This information was requested by Mr. J. Wetmore and others of your staf f in a phone conversation with Mr. R.
Shimshak, LACBWR Plant Superintendent, on December 18, 1978.
Please contact us if additional information is required.
Very truly yours, DAIRYLAND POWER COOPERATIVE
.Addl I
v Frank Linder, General Manager FL:NLH:af Enclosure cc:
(See attached list).
7 9 0 2 2 6 0 ey'#6
Director of Nuclear Reactor Regulation LAC-6118 Washington, D. C.
20555 February 14, 1979 cc:
J. G.
Keppler, Regional Director U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Charles Bechhoefer, Esq., Chairman Atomic Safety and Licensing Board Panel U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Ralph S.
Decker Route 4 Box 190D Cambridge, MD 21613 Dr. George C. Anderson Department of Oceanography University of Wushington Seattle, Washington 98195 O.
S.
Hie s ta r.d, Jr.
Attorney at Law Morgan, Lewis & Bockius 1800 M.
Street, N. W.
Washington, D. C.
20036 Kevin P. Gallen ttorney at Law
. organ, Lewis & Bcckius 1800 M Street, N. W.
Washington, D. C.
20036 Coulee Region Energy Coalition P. O. Box 1583 La Crosse, WI 54601 Response to NRC Request for Additional Information Concerning Seismic Analysis and Modification of FESW Drain Line Proposed Modification - LACBWR Spent Fuel Storage NRC Items 1 and 2 Reg. Guide 1.26 classifies SFP drain line ac Class 3, i.e.,
ASME Code Subsection ND.
Therefore, provide the loading combin-ations (per piping design spec. ) for a Class 3 piping sys tem and the correspcnding service (s trcos ) limits for the design, normal, upset, emergency, and faulted conditions.
Provide the max. cal-culated stress for cach condition.
Note:
Designing to NB does not qualify piping for NC or ND since all of NB must be utilized, e.g.,
Fab. 8 In s ta l la tio n, Testing (NDE), GA, etc. (NA 2134).
Per Reg. Guide 1.92, all three directions of carthquake must be applied simultaneously, including seismic anchor movement.
DPC RESPONSE:
The seismic and stress analysis of the LACBWR spent fuel storage pool drain line (SFP drain line) given in NES report 81A0032, Rev. 0 (Reference 1) was performed for the drain line with a single check valve.
In order to meet the single failure criteria, the SFP drain line will be provided with two check valves as shown in Figure 1.
The seismic analysis of the modified SFP drain line (with two check valves) has been performed in accordancu with the requirements of Regulatory Guide 1.92 (all three directions of earthquake applied simultaneously).
The stresses due to various loading conditions have been combined and compared with the allowable stress values in accordance with the requirements of ASME Code Subsection ND for Class 3 piping systems.
The mathematical model of the SFP drain line for seismic and stress analysis is shown in Figure 1.
The results of the analysis are contained in Reference 2 and are summarized in Table 1 through Table 4.
From these tables it can be seen that the maximum deflections of the SFP drain line are nominal and the maximum stresses due to seismic, dead weight, pressure and thermal expansion loadings, combined in accordance with ASME Code Section III rules for Class 3 piping system satisfy Code design requirements.
References:
1.
Nuclear Energy Services, Inc. Document No. 81A0032, Rev.
O,
" Seismic and Stress Analysis of the LACBWR Spent Fuel Storage Pool Drain Line".
November 17, 1978.
2.
LACBWR Fuel Storage Pool Drain Line, Project 5101, Task 035, PIPESD Computer Run No. Gary 01Z dated 1/26/79, NES Computer Output Binder No. S-36.
NRC Item No. 3 Provide physical details of anchor at forced circulation pump cubicie vall.
Ve rify that the anchor vill retain its structural integrity and perform its function during and follouing an SSE.
DPC RESPONSE:
As shown in Figure 2, the fuel storage pool drain line is buried 4'-0" in the 2'-10" thick forced circulation pump cubicle wall (Concrete was poured with the SFP drain line in place).
The SFP drain line/ concrete wall interface provide natural anchor for the SFP drain line.
The reaction loads at the anchor point from the 4 inch diameter SFP drain line are quite small (maximum moment of 22.66 k-in.) to have any effect on the structural integrity of the anchor point or the concrete wall.
NRC Item No. 4 Valve operability - If valve is normally closed and does not have to perform a mechanical motion to perform its safety related function, i.e., keep SFP from draining, then it does not have to be qualified.
DPC RESPONSE:
The check valves to be installed in the LACBWR fuel pool drain line will be normally open and must close to perform their safety related function.
Accordingly, the valves will be qualified to operate dur-ing a seismic event.
Additionally, provisions will be included to permit periodic testing of the check valves to ensure their oper-ability.
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TABLE 1 NATURAL F R E 2 ul:MCIES OF VI DI ATIO::
MODE ti o.
F R E 7 '. d !! C ; (CPS) 1 6.44 2
13.36 3
19,02 4
24.62 5
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T A E L '. 2 MAXIMU:' DE F LI:CT I O '
Load Condition t!o d e ::o,
Maxinun Deilection (Inchen)
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Dead Weight & Sunt.ained Mechanical Loads 7
-0.0021
-0.3304
,.0111 Thermal Expannion G
0.0599
-0.0040 0.0174 Seismic Load (1/2 ESI )
7 0.0142 0.0i20 0. 'J ') 3 0 Seismic Load ( f; S E )
7 0.0247 0.1413
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TABLE 3 f t AXI MUM LOIIG ITU D III A L STRESS Load Condition 1:o d e :o.
Maximum S t r e r. s (ksi)
Dead Weight & Sustained 2
7.17
!!c c h a n i c a l Loads Thermal Expansion G
2.11 Seisnic Anchor Movement 3
1.97 (1/2 SSE)
X+Y+Z Seismic 2
1.54 (1/2 SSE)
X+Y+Z Seismic 2
3.07 (SSE)
x TABLE 4 s
ASME CODE CLASS 3 PIPING STRESS ANALYSIS SU :XARY Pressure, Weight, Other Thermal Expansion & Seismic Sustained Loads & Thermal stained Loads (Equation 8)
Occasional Loads (Equation 9)
Anchor Movemtat Equation (10)
Expansion * (Equation 11) e Calculated Allowable Node Calculated Allowable Node Calculated Allowable Node Calculated Allowable Stress (ksi)
Stress (ksi)
No.
Stress (ksi)
Stress (ksi)
No.
Stress (ksi)
Stress (ksi)
No.
Stress Stress (ksi) 5.46 S =15.7 2
6.95 1.2S =18.84 7
4.95 S =20.0 2
10.26 S.+S =35.7 h
h A-a h
N.A N.A.
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N.A.
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N.A 2
8.1 2.4S 37.68 N.A N.A f A N.A h
he nomenclature, conditions, ecuation number and application of the above limits are in ccordance with ASME Section III ND-3600 (With Addenda).
ue no loadings associated with :mergency plant condition for SFP drainline.
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