ML20028E311
| ML20028E311 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/19/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8301210206 | |
| Download: ML20028E311 (42) | |
Text
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DUKE POWER Go>nwxy P.O. Box 331130 CIIAHLOTTE. N.C. 2(1242 IIAL II. TUCKEH TEI2PIlONE vses ..rserne=r (704) 373-45:M
..m,m. . m o, ,
January 19, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
In order to facilitate the completion of the review of the Catawba FSAR, Duke Power Company is transmitting herewith responses or revised responses to open items of the following technical review branches. Attachment 1 - Geotechnical Engineering Attachment 2 - Power Systems These respcl1ses will be included in FSAR Revision 7. Very truly yours, lfd/ $ hChW Hal B. Tucker g ROS/php Attachments cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq. Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 DO 8301210206 830119 PDR ADOCK 05000413 A PDR
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w Mr. Harold R. Denton, Director January 19, 1983 Page 2 r cc: Palmetto Alliance 2135h Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman l Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207 i
Attachment I Geotechnical Engineering Branch
i . l
+
l l M ATERIAL REMOVED. MATERIAL' REMOVED, OR MOISTURE CONTENT OH MOISTURE CONTENT A DJ U ST E D, M ATERIAL ALLOWABLE DEVIATION FROM ADJUSTED, MATERIAL RETESTED & COMPACTED , OPT. MOISTURE CONTENT _ RETESTED & COMPACTED I I 220- l l l 1 200-1 1 180- l l l 1 i l l ., 16 0- l l l l 14 0-y l l
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NUMBER OF MOISTURE TESTS VERSUS MOISTURE CONTENT FOR g'~ ' COMPACTFD GROUP I BACKFILL CATAWBA NUCLEAR STATION W govu rowt a i Figure 2.5.4-19 Revision 7 New Figure -
4 l e MATEhlAL5 BELOW SP Etif IC AT ION LlulTT, J WERE RECJMPACTED ulNIMUM SPECIFIC ATI)N GR REM >vtD RE ;UIREMENT (96% ) 1 200- I l l l l
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[ MATERIALS l 40-- REMOVED OR RECOMPACTED) lg 30 -- l 20 -- l i lO-- l i s' i i i i i 80% 90*4 10 0 *4 110 % 120*4 > l30% RELATIVE DENSITY NUMBER OF COMPACTION TESTS VERSUS RELATIVE DENSITY M' 'g FOR GRANULAR BACKFILL fc' at e: win, , l CATAWBA NUCLEAR STATION C,.' Figure 2.5.4-21 Revision 7 New Figure "
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[ I LAKE WVL/E MAX. D D. EL. 5670 s p3 Pl P2 p7 ZONED e MAX. EXPECTED DD. Fi.559.4 EL.904 0s P5 P6 BLANKET ORAI _(SEE DETAIL)g eMAX.D.D.(LOSS _QF LAKE WYLIEL d __ _ .'- EORIG.- LAKE
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ET DRAIN FOLLOWS THE CONTOUR OF THE NATURAL LAKE BOTTOM ABOVE EL.545.0 AND EXISTS BETWEEN EL.545.0 8 EL.570.0 ORIGINAL GRADE AS FOLLOWS S.N.S.W. POND DAM BLANKET DRAIN BEGINS AT EL.570.0 AT STATION O.50; SLOPES TO EL.545.0 TYPICAL SECTION AT STATION 2*OO; LEVEL AT EL. 545.0 BETWEEN STATIONS 2+00 AND4.OO; 30 0 30 60 SUDPES TO EL.560.0 AT STATION 5 00; THENCE TO EL.570.0 ATSTATlON 7 00
*** '"' A TOE DRAIN IS CONSTRUCTED ABOVE.
EL.570.0 ORIGINAL GRADE. SNSW POND DAM TYPICAL SECTION e CATAWBA Figure 2.5.6-1 NUCL Revision 7
A 2.5 - K lp
- DATA FOR K = g 1.0 INCORPOR ATES A Borrow Dry Unit -c d CO R R ECTION FACTOR OF 0.70 APPLIED ZMe IdLcation Weiaht. PCF M* M 1.75 2a TO MEASURED SHE AR STRESSES Embankment G en e ral *
- 111 8 Y E ** SAMPLES TESTED FOR CYCLIC STRENGTH o N.1 106-113 O T l DURING PSAR INVESTIG ATION 5 Cooling Tower 116-117 @
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- :--=-=-- -- - - -- 'l Kg= 2.0 5
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, gA CYCLIC STREfiGTH OF S0ILS
% CATAWBA NUCLEAR STATION j -- Figure 2.5.6-14 l
1 Revision 7 o
l . l l 9 MATERIAL REMOVED, ALLOWABLE DEVtATION MATERIAL REMWED. OR MOLSTURE OR MOISTURE CONTENT FROM OPT. MOISTURE CONTENT ADJUSTED, MATERIAL ASAETED, MATERtAL CONTENT _ RETE _ST_ED AND COMF%CTED l 2% _ RETESTED S COMPACTED 200 - 180 l l 16 0 - l l 1 14 0-0 l l h120
- u. I 100- l m
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-5 DEVIATION FROM OPTIMUM MOISTURE CONTENT (%)
NUMBER OF MOISURE TESTS $ VERSUS MOISTURE CONTENT !; FOR STANDBY NUCLEAR -. i.
, '.s SERVICE WATER POND DAM I 1[
. ' ' Of W
DH E h t) CATAWBA NUCLEAR STATION Figure 2.5.6-34A n 1as
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cr 40-i i l 30- ; I l i 20 - l I I i i 10~ l Ii I m .
-5 -4 -3 -2 -i 9'6 *i +2 +3 +4 +5 +6 +i +8 +9 DEVIATION FROM MINIMUM SPECIFIED PERCENT COMPACTION N;MBER OF COMPACTION TESTS VERSUS PERCENT COMPACTION FOR STANDBY NUCLEAR SERVICE
- w WATER POND DAM ovat? I' N' CATAWBA NUCLEAR Figure 2.5.6-34B STATION Revision 7 New Figure
m G = 1000 K2 (om) PSI 1600 7 1200 LEGEND: Q Partially Weathe, red Rock K2= 140 (Setsmic) h Residual Foundation Soils- Saprolites K y= 70 (Seismic) 800 0 Embankment Soils- Resonant Column and Cyclic Triaxial Tests K = 40 2 V Q Finn Residual Foundation Soil- Resonant Column Tests Material of This Test is Remosed in Foundation Preparation Due to 40o 7 xNSPT .< 15 lilows
? ? / 4 ?
280 Typical Published Value of K 2 max. Material Kg Reference
'240 Very Dense 70 Seed & Idriss,1970 h Sand, Dr=907o 200 160 g 120 ^
l'artially Weathered R k V g .A, S >ils - ap olites 40 ~~ % td
- Embankment Soils *% L 0 'G~'
10 4 10 3 Ig2 ggi g Shear Strain, t - Percent (Added Data From floring A-105) DYNAMIC MODULUS FOR EMBANKMENT AND m FOUNDATION MATERIALS nunt rhet's CATAWBA NUCLEAR STATION _ _, / Figure 2.5.6-40 Revision 7 l
I I I I I & I I I I I I I I I I I Depth ~ 150 - Boring Data Feet Description 100 A10352 UD-Lab 33.4-35.3 Saprolite _
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'Carows: Figure 2.5.6-40A Revision 7 l
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- O TP-19,2 to 3 Ft. (Compacted)
O A-103S2,23 to 25 Ft,- UD Sample ' g A-103S2,33.4 to 35.3 Ft.- UD Sample - o A-103S2,44.3 to 45.9 Ft. - US Sample ' , f , 25 -
./ /" M st Probable __
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' Rock weathered m FOUNDATION MATERIALS During SSE Saprolite M e
[mt ern CATAWBA NUCLEAR STATION MP value of High G c, D Embankment I
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( i SYNTHETIC EQ-1 o i I h treet CATAWBA NUCLEAR STATION
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? Figure 2.5.6-49A Revision 7 New Figure 5~
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, saf CATAWBA NUCLEAR STATION Figure 2.5.6-498 Revision 7 3 New Figure
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SYNTHETIC EQ-3 o t CATAWBA NUCLEAR STATION Figure 2.5.6-49C g Revision 7 New Figure f' 8 -
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-' Figure 2.5.6-49D o Revision 7
$ New Figure i~
8
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% tc 1.Js 2.60 4.c2 5.3G 6.1C 8.ca 9.M 1c.72 12.06 13.s0 :4.14 :6.ta :1.42 :e.76 2; . ' O T!NE.!SEC.51 i
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Finite Element Analysis Results 0.386g 0.404g 0 l I I I I I I I l 595 Ft.
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0.4 - Seed Da ta 7 -
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Used for
! Catawba /:SW 0.8 Pond Dam
[ _
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1.0 : I / _l 1 I i 1 Eleva tic;n 0 0.2 0.4 0.6 0.8 1.0 510 Ft. Kmax/U max
Reference:
Makdisi, F. I., and Seed, II . B., " A Simplified Proc.cdure for Estimating Earthquake - Induced Deforma-tions in Dams and Enhankments", Repo"t SEISMIC COEFFICIErlT f:o . UCD/EERC 77-19, College of SNSW P0fl0 DAM Engineering, University of California, Berkeley, August, 1977. oudrome CATAWBA NUCLEAR STATION Figure 2.5.6-50A Revision 7 tiew Figure
- g. m /
= ,
-e 460 - -
660 640 - - 640 420 - - 620 600 - C R EST ELE V ATION
- 59 5.0 - 600 3 _ \_ 3
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71.78 1.s s 1.49 1.35 1.24 1.06 1.16 1.26 1.37 1.54 N 1.16 1.11 1.s 9 2.21 1.80 % g1.4 2 1.44 1.57 1.70 2.03 2.0 s 1.91 1.75 1.5 s 1.41 1.32 1.25 1.20 1.14 1.24 1.'37 1.47 1.5s 1.77 2.14 2.72 3.17 2.00 156 1.52 l
,,. _ ----* ,,0
>. 4; _
s0s _ _ s00 ese - - 440 i g i i t i 1 j i
-47s -200 100 0 100 200 438 I
LOCAL SAFETY FACTORS i AGAINST 5% STRAIN om ro CATAWBA NUCLEAR STATION Figure 2.5.6-52 , Revision 7
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\
Attachment 2 Power Systems Branch I i l
o 4 CNS 9.5.3 LIGHTING SYSTEMS The plant is provided with adequate illumination through the integrated use of normal and emergency lighting systems. These lighting systems provide illumination for normal and emergency plant operation. 9.5.3.1 Normal Lighting System The Normal Lighting System provides general illumination throughout the plant in accordance with the illumination levels recommended by the Illuminating Engineering Society. Power to the Normal Lighting System is supplied from independent 600VAC motor control centers through individual 600-208Y/120VAC l dry-type transformers located in selected areas throughout the plant. All 4 lighting in the Reactor Building is incandescent, while incandescent, floure-scent, and high intensity discharge (HID) lighting is provided for the Auxil-iary and Turbine Buildings. Normal lighting panelboards and their associated transformers and motor control centers are located such that a single failure in the Normal Lighting System will not result in a total loss of illumination in any area. 9.5.3.2 Emergency Lighting Systems 9.5.3.2.1 Design Bases The emergency lighting systems are designed to assure that adequate lighting is provided in all vital areas of the plant including essential access routes to these areas. A single failure analysis of the emergency lighting system is provided in Table 9.5.3-1. 9.5.3.2.2 Emergency 250VDC Lighting System l The Emergency 250VDC Lighting System provides general emergency lighting for the control room and selected stairways and corridors throughout the plant. Voltage sensing relays automatically energize the normally deenergized emer-gency DC lighting system in the event of a loss of normal lighting. Power to the Emergency 250VDC Lighting System is from the 250VDC Auxiliary Power System as described in Section 8.3.2. Emergency 250VDC Lighting available Q430.57 for a safe shutdown condition is shown in Table 9.5.2-2. 9.5.3.2.3 Emergency 208Y/120VAC Lighting System The Emergency 208Y/120VAC Lighting System provides general emergency lighting in the control room, stair, exits, corridors, and manned safe shutdown areas as listed in Table 9.5.2-2. Q430.57 9.5-7 Rev. 7
1
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CNS The emergency AC lighting is divided into two independent trains (A and B) arranged such that a single failure will not result in a total loss of il-lumination in any area served. Voltage sensing relays automatically energize the normally deenergized emergency AC lighting in the event of a loss of normal lighting. Power to train A and B of the Emergency 208Y/120VAC Light System is from the A and B diesel generators, respectively, through inde-pendent trains of the Essential Auxiliary Power System as described in Section 8.3.1. 9.5.3.2.4 Emergency 8 Hour Battery Lighting The Emergency 8 Hour Battery Lighting System is provided specifically for Q430.56 station illumination and access / egress for safe shutdown of the plant and for any other emergency situations that may arise. This safe shutdown and ther emergency lighting is provided in the control room, access and egress 0430*57 stairs, exits, and corridors, and manned safe shutdown areas as listed in Table 9.5.2-2. The 8 Hour Battery Lighting System consists of individual 200 watt, self-contained, sealed lead calcium battery units. The units are normally on con-tinuous charge from the unit normal auxiliary power system. Upon loss of normal voltage these are energized. Means are provided to test each light-ing unit individually. t 9.5.4 DIESEL GENERATOR ENGINE FUEL DIL SYSTEM 9.5.4.1 Design Bases The Diesel Generator Engine Fuel Oil System is designed to provide for the storage of a seven-day supply of fuel oil for each diesel generator engine and
- to supply the fuel oil to the engine, as necessary, to drive the emergency generator. The system is designed to meet the single failure criterion, and to withstand the effects of natural phenomena without the loss of operability.
l 9.5-8 Rev. 7
-. _-__ ____,o--,,,,,,
o A TABLE 9.5.2-1 , COMitNICATIONi AVAILABLE FOR TRANSIENT AND ACCIDENT CONDITIONS i Sound-Po.ered Erpected Noise Telephone - Sound-Powered Microwave Utilizing A Emergenc, Maintenance PA via FABA Dispatch Weighting db PABR Telephone Circuit Circuit PA System Telephone Phone Location tevels3 (% DEA)' (llodBA)' ( 110dB A ) ' (95dBA)' ( 95dB A ) ' ,2 (76dBA)8 i Auxiliary feedwater pump turbine panel. .95db M M X X Ausi!iary shutdown paneI rooms. .70db X X X X Control room. .62db x x X X X x DieseI generator rooms. .105db x 4 X X fuel pool area .76db X M x X HVAC equipment room control paneIs. .70db A x X Instr ument ai r compr es snrs. .90db X A X Sw i t c hqua t and motor cont r ol center rooms. ./Odb i 4 X X Valves IND26, IND/7 IND60, & l IND61 in the Residual Heat Removal System. 95db < x X Valves INC56A and IRC818 in the Component Cooling Watei System. .96db F M X Valves IV015B. IVQ16A. & IVQ13 in the Containment Air Relvase and Addition System. .94db x X X Reactor Coolant System Pressure l Gage. .100db W X primiry 5 ample Sink. .75db x X X { tett rical Penetration Room. .75db X X X Centrol Room Annex. .62db x X X fi.9 KV Switchgear Room. . 75eth x X X RC lemperature H&C Connection Box .lo db P X l Residuil Heat Removal be,it enchanger outlet temperature. 90db X X
"- NOTE 5: 1) Maximum noise level c apihilit ies et eq .s i pme n t . 2) lelephones equipped with t ransistor amplif ier and ,ise cancelling transmitter. e-
- 3) Noise levels iesult of mo nuvements t ak en at cnmp irible plants. 4) After a unit is eper ational, plant noise levels will be measured during neimal and simulated <hotdown conditinns. Sound isolation booths or noise carcelling devices will then be added as ne( e s sa r y . $) hatuj Held R3ij i n s pe avai l 3 tile tu plant potsonnel.
Rev. 7}}