ML20031B973
| ML20031B973 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/01/1981 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-81-113, NUDOCS 8110060325 | |
| Download: ML20031B973 (6) | |
Text
- _ _
?
KANSAS GAS AND ELECTRIC COMPANY T&4 ( LT f 7 5 Ht: ( 4 WNANv OLENN L KOESTER
%CEPet&@fmf newCLEen October 1, 1981 4
(O g
Nr. Harold R. Denton, Director b
Office of Nuclear Reactor Regulation J
d.S. Nuclear Regulatory Commission g
Washington, D.C.
20555 OCT U
r 6 79OlA 6
- g. 4 D 'Ctr KENRC 81-113 Re:
Docket No. STN 50-482 A
\\D Ref: 1) Letter dated 8/7/81 from RLTedesco, NR
\\
'6 8
to GLKoester, KG&E
- 2) Letter KMLNRC 81-110 dated 9/10/81 from GLKoester, KG&E, to HRDenton, NRC Subj: Geotechnical Engineering
Dear Mr. Denton:
The Referenced 2) Letter transmitted responses to NRC questions in the area of geotechnical engineering. Transmitted herewith is the outstanding response to question 241.5 WC, items 4 and 5.
The remaining response to question 241.5 WC, items 2 and 3, will be forwarded to you on October 28, 1981. This infor: nation will be formally incorporated into the Wolf Creek Generating Station, Unit No. 1, Final Safety Analysis Report in Revision 6.
This information is hereby incorporated into the Wolf Creek Generating Station, Unit No.1, Operating License Application.
Yours very truly, GLK:bb cc: Dr. Gordon Edison (2)
Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 g/
Mr. Thomas Vandel Resident NRC Inspector g
Box 311 l
8110060325 811ceY nurlingt n, Kansas 66839 PDR ADOCK 05000482 A
- pp
_a 201 N Market - Wochuta. Kartsas - Mad Address-PO Bos 708 i Wochda. Kar sat 67201 - Te+ phone ken Corte 1316) 2F t kss t
~ fT f
j
+-
1 i
OATH OF AFFIRMATION l'
STATE OF KAN.'AS-
)
l'SS:
COUNTY OF SEDGWICK )
I,' Glenn L. Koester, of -lawful age, being duly sworn upon oath, do depose, state and affirm that I am Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of-transmittal, know the contents thereof, and that all statements contained therein are true.
t KANSAS GAS AND ELECTRIC COMPANY
~14/99 D
By,
Glenn L'.
Koester
~
Vice President - Nuclear W.B. Walker, Secretary STATE OF KANSAS
)
) SS:
COUNTY OF SEDGWICK )
BE IT REMEMBERED that on this 1st day of October, 1981 before me, Evelyn L. Fry, a Notary, personally appeared Glenn L.
Koester, Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, who is personally known to me and who executed the foregoing instrument,
-and he duly acknowledged the execution of the same for and on behalf of and as the act and deed of said corporation.
IN WITNESS WHEREOF,_I have hereunto set my hand and affixed my seal the
,,..*f," *ldat;g and year above written.
' '.,{.
{ s s u A,i
,y A f 1 i
w :. u y,_ g l evFvn 'pn. n tag t._ p
. oa.
o
'6I. l}<{.
,p, f},coinmission expires on August -15,1985.
h a
l SNUPPS-WC Q241.5 1.
In Figure 2.5-47 show locations and limits of soft material, if any, that was replaced by '
competent material durina construction.
2.
For the ECCS pipeline, provide typical trans-verse cross section showing the excavation s'
limits, pipe, bedding, and different kinds of backfill materials.
3.
Provide typical longitudinal section and cross section details of excavation and back-fill near the interface between the ECCS pipes and the structures.
4 What are the estimated total and differential settlements of the ECCS pipe and the struc-tures at their interface due to both static and dynamic loads?
5.
What is the estimated settlement of the ECCS piping due to both static and dynamic loads?
'R241.5 1.
No soft material was encountered.
2.
Response to be provided by October 28, 1981.
3.
Response to be provided by October 28, 1981.
4.
The settlements for the ECCS pipeline have been calculated near the connection points at
.the control building and the ESWS pumphouse.
At the control building, the static settle-ment caused by the structures is calculated to bu 0.2 inch.
The calculation also shows that the settlement at a distance of 20 feet from the control building is approximately 0.1 inch.
Settlement of the pipe close to the building from backfilling above the pipe was computed to be on the order of 0.1 inch.
Therefore, it is concluded that the total and differential settlements of the ECCS pipeline caused by static loads will be less than the total settlement of the control building (i.e.
less than 0.2 inch).
Settlements of the pipeline from dynamic loads are negligi-ble (see Question 5).
Settlements of the control building during dynamic loadings will be elastic and recoverable with maximum de-flection computed to be less than 0.1 inch.
The settlement computations for the ESWS pump-house show that the settlements of the ESWS pumphouse structure will be less than 0.25 inch.
The settlement of the ECCS pipe next Rev. 6 241-7 10/81
f A
SNUPPS WC R241.5 4.
(continued) to the ESWS pumphouse is computed to be on
.the order of 0.1 inch.
Total and differ-ential settlements of the pipe at the ESWS pumphouse structure will, therefore, be on s
the order of 0.1 inch.
The settlement of the ECCS pipe under dynamic loads will be
. negligible (see Question 5).
The settlement of the pumphouse during dynamic loading will be less than 0.1 inch.
Total and differen-tial settlements' of the ECCS pipe and the ESWS pumphouse structure will, therefore, be less than 0.1 inch.
Total and differential settlement at the ESWS discharge structure will be negligible under
-both static and dynamic loads.
5.
The ECCS pipeline is founded on a maximum of 12 inches of pipe bedding over bedrock or structural fill.
Since the combined weight of the piping and the backfill is approximate-ly equal to the removed overburden, any set-tlement occurring from static loads will be due to the compression of the underlying material from the weight of the backfill.
On this basis settlements along the pipeline are negligible.
Settlements close to the struc-tures (control building and ESWS pumphouse) where the thickness of the structural fill underlying the pipe is between LO ard 20 feet is calculated to be on the order of 0.1 inch.
The pipe bedding is compacted to 80 percent relative density.
The structural fill is placed at 95 percent of the maximum dry den-sity as determined by ASTM-D1557 (Modified Proctor).
Recent correlations between rela-tive density and Modified Proctor tests show this density corresponds closely to 100 per-cent relative density (see Table 241.5-1).
No settlement due to compaction from dynamic load is, therefore, anticipated for the structural fill.
Any settlements due to dynamic loads will arise from compaction of the granular pipe bedding under the pipeline.
Settlement cal-culations
- were, therefore, performed in accordance with Silver and Seed (1971) and Pyke, et'al (1975).
These calculations show that the settlements of the ECCS pipeline from dynamic loads will be negligible.
Rev. 6 241-8 10/81
.7 0-f SNUPPS-WC n
R241.5-
.5.
-(continued)
REFERENCES p
- Pyke, Robert,
- Seed, H.
- Bolton, and Chan, Clarence K.,
1975, " Settlement of Sands Under s
Multidirectional Shaking",
Journal of the Geotechnical Engineering Division, volume 301, no. GT4,. American Society of Civil Engineers, pp 279-398.
I
- Cilver, Marshall-L.,
and Seed, H.
- Bolton, 1971, " Volume Changes in Sands During Cyclic Leading",
Journal of the Soil Mechanics and Foundation Division, volume 97, no.
- SM9, American Society of Civil Engineers, pp 1171-1182.
O 1
6 Rev. 6 241-9 10/81 L_'.
SNUPPS-WC TABLE 241.5-1 RESULTS OF DENSITY TEST MAXIMUM DRY MAXIMUM / MINIMUM 95 PERCENT OF' MODIFIED PROCTOR MATERIAL DENSITY, PCF.
DRY DENSIT, PCF EXPRESSED AS RELATIVE DENSITY NO.
ASTM-D1557 ASTM-D2049 1
140.6 136.0/101.8 94 2
140.8 135.5/102.4 96 3
147.0 139.2/105.1 101 4
142.6 131.9/105.3 110 Report " Field Density and Laboratory Investigation of the Crushed Stone Pill, Callairay Plant Units 1 and 2".
Dames & Moore Report for Union Electric Company dated August c.
1975.
Tests on CCFI Material, Marble Hill Nuclear Power Plant.
Wet Method.
4 O
e Rev. 6 10/81
-.