ML20105C603
| ML20105C603 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/11/1992 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20105C562 | List: |
| References | |
| NUDOCS 9209220320 | |
| Download: ML20105C603 (9) | |
Text
{{#Wiki_filter:- --- - . . . - . . Docket Number 50-346 Licen'se Number NPF-3
%rta! Number 2037 ,
sttachment Page 5 v l 5.0 :ESIG'i FEATUDES 5.1 IITE ' EXCLUSION AREA asde6cd in lDCFA Sd 100, l 5.1. The exclusion area is 3sh;ar, cc, Tigure 5.' - ' l r LOW FOPULATION ZONE i as c;eG neA in IDCFR Ikrf 100. 5.1.2 The low population zone isjsho'. r. or 9;urc 5.'-2. T hMcal l'O' p c\eEO CA h*ge.ction I. : SITE EDUNDARY , ppact { l ,h ns , ; , a 5.1. 3 The UNRESTRICTED AREA _an(SITE BOUNDARY /for radioactive licuid effluents T is 3r.cwn on Figure 5.1-3. The UNRESTRICTED AREA ano SITE BOUNDARY for radio-
%acti e gaseous effluents is shown on Figure 5.1-4. ,
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- 5. 2 :JNTAINMENT CONF:3URATION
- 5. 2. '. The containment structure is compris?d of a steel containment vessel, i having the snape of a right circular cylinder with a hemispherical dome and I elli;:isodal bottom, surrounded by a reinforced concrete shield building. i 5.2.1.1 CONTAINMENT VESSEL
- 2. Nominal inside diameter = 130 feet.
Nominal inside height = 285.5 feet.
- . 6 Net free volume = 2.834 x 10 cubic feet, f Nominal thickness of vessel walls - 1 1/2 inches. i
- e. Nominal thickness of vessel dome - 13/15 inches.
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- f. Nominal thickness of vessel bot ;om - 1 1/2 inches. i 5.2.'. 2 SHIELO BUILDING
- a. Minimum annular spr.ce = 4.5 feet.
- b. Annulus nominal volume = 678,700 cubic feet.
- c. Nominal outside height (measured from top of foundation base '
to the top of the dome) = 279.5 feet. i
- d. Nominal inside diameter ='139.25 feet.
- e. Cylinder wall minimum thickness = 2.5 feet.
-f. Dome minimum thickness = 2.0 feet.
- g. Dome inside radius = 125.29 feet.
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Docket Number 50-346 ' License Number NPF-3 Scrial Number 2037 Attachment rue w { INFORMATION ONLY DEFINITIONS
,1.29 Deleted ,
;jPROCESS CONTROL PROGRAM 1
i'l.30 The PROCESS CONTROL PROGRAM (PCP) shall contain the current fonnulas, j sampling, analyses, tests, and determinations to be made to ensure that processing ano packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 State regulation 1, burial ground requirements, and other requirements governing tne disposal of solid radioactive waste. l 1.31 Deleted l 0FFSITE DOSE CALCULATION MANUAL (00CM) l 1.32 The 0FFSITE ME CALCULATION MANUAL (0DCM) shall contain the methodology l
= i and parameters used in ne calculation af offsite doses resulting from radio-
; active gaseous and licuid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setooints, ano in the conduct of the Environ-4 mental Radiological Monitoring Program. The ODCM shall also contain (1) the
' Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions v# the information
, that should be included in the Annual Radiological Envirorsnental Operating l
and Semiannual Radioactive Effluent Release Reports rcquired by Specifications j 6.9.1.10 a 6.S.1.11. t j '1. 33 Deleted I 4 i ' I l 1.34 i Deleted Deleted , l l1.35 l.36 Deleted l MEMBER (S) 0F THE PUBLIC 1.37 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupation-ally associated with the plant. This category does not include employees of ne utility, its contractors or vendors. Also exciuded from this category j are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recrea-tional, occupatioral or other purposes not associated with the plant l SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by tne licensee. v DAVIS-BESSE, UNIT 1 1-6a Amenoment No. 26,170 '
~~~ ~ ~~' ~~~ ~~~ "' ~ ! Docket Number 50-346 I License Number NPF.3 4 . . serial, Number 2037 i Attachment i DEFINITIONS FOR INFORMATION '
UNRESTRINED AREA i l' 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUCARY l access to which is not cor, trolled by the licensee for pu. poses of protection ~ ! i of individuals from> exposure to radiation and radioactive matterials, or any ! ! area withim the SliE. BOUNDARY. used: for residendalequarters or: for industri&s > i commercial, institutional, and/or recreational. purposes. The definition of - [
- UNRESTRICTEII AREA:usein implementing the Radiological . Effluent Technical .
l
.j Specifications has been. expanded over that:iml0e CFR.420.3(a)(17). The .
! UNRESTRICTED AREAt boundary may coincide witir the exclusiorr-(fenced) area- ! j i boundary, as defined in 10 CFR 100.3(a), but the. UNRESTRICTED AREA does not- ! 1 include areas over wate.- bodies. The concept cf UNRESTRICTED AREAS, estab- , ! j lished at or beyond the SITE BOUNDARY, is utilized in the LIMITING CONDITIONS. ' ! FOR OPERATION to keep levels of radioactive materials in liquid and gaseous - effluents as low as is reasonably achievable,. pursuant to 1C CFR 50.36a. j l> } 1.40 Deleted 4 l ! CORE OPERATING LIMITS' REPORT
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1.41 The CORE OPERATING LIMITS REPORT is the unit-specific. document that li provides core operating. limits for the current reload cycle. These. cycle-
- 4 specific core operating limits shal's be detennined for each reload cycle in i accordance with Specification 6.9.1.7. Plant operation within these core- ,
j operating limits is addressed in individual specifications. l l-i i i- ! i . i ! ( >
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i i r 4 t i : i I l DAVIS-BESSE, UNIT 1- .1-6b Amendment No'. ; M.JM,170 : s
1 Docket Number 50-346 License Number NPF-3 s'ecial liumber 2037 Attachment FOR !NFORMAT - i
- Page 12 N 2 WILE RA0lVS .
! NNW NNE ! I ! i o
- NW ig* 0 NE l
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- INDICATES SEGNEXT SUBJECT [
' $ TO SEASONAL INCREASE DUf'NG r suuu!R 50NTVS i ! SEE Taol. 2.1-5 i I ' 1 5 PERMANENT POPULATION PROJECTION ! ANNULI
- i. lELLS 1171 M 1110. M M
! 0-1 18 1 181 181 211 277 i
! 1-2 410 410 410 47 1 505 !
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li TOTAL 591 591 591 EB2 733 I j- t i
- FOR SEONENT O!STRIBUTION IN FUTURE YEAR $ SEE Table 2.1-2 j j FOR SEASONAL INCREASE. IN RESIDENT POPUL All0N 00RINr ;UMER MONTHS SEE Taele 2.1-5 ,
1 - i DAVIS BESSE NUCLEAR POWER STATION
- LOW POPULAT10N ZONE FIGURE 2.1 i.
REVISION 0 JULY M82 :
I Dxket Number 50-346 License Number NPF-3 4
; Seri l Number 2037 i Attachment I
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i , 'I I DAVIS-BESSE NUCLEAR POWER STATION SITE ARRAM.;EMENT : l FIGURE 2.1 3 i l > l. (. + 1 ' REVISION I I JULY 1983.
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