ML20236H264
| ML20236H264 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/02/1998 |
| From: | Covill D, Lehmann G, Miller R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20236H176 | List: |
| References | |
| C1101-221-E520, C1101-221-E520-013, C1101-221-E520-13, NUDOCS 9807070141 | |
| Download: ML20236H264 (10) | |
Text
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1920-98-20326 Attactment II T
GPU ""
CALCULATION COVER SHEET Calculaton Number Rev.# System Number (s)
C-1101-221-E520 013 / l s,1me..dtf 221 Sheet 1 of 9 Calculaton Subject TMI-1 Reactor Vessel Welds Fluence, RTm and RT,,oy per R.G.1.99 R-2, Pos. No.1.
YES NO is this calculation within the OQA Plan Scope?
x (If Yes, a venficabon is required) i l
Does this calculation contain assumphons/ design input that requires confirmabon' l
t (if Yes, provide EDTTS No.(s)) O @
is this calculaton performed as a design basis calculabon?
(if yes, identfy design basis parameters (section 3.3))
X 0
Reactor Vessel P/T Limits. Tech Spec. Section No. 3.1.2 Reference Source Documents (calculations, safety evaluatons) (Secton 4.3.1.3)
DOCUMENT NO REV NO BAW-2108. Rev.1, May,1992 B&W Owners Gp Matenals Committee report, Rev.1
" Fluence Tracking Sytem".
GPUN Calc. No. C-1101-221-5300011 Rev. 0.dtd 1/18/93, Sub.: "TMI-1 Reactor Rev.O Vessel Welds Fluence and RTNDT per R.G.1.99 R-2, versus Time" l
APPROVALS:
i n -
Onginator George L. Lehmann DATE 2/18/98 V.,, ir 2- - Engener/Recr;;r Richard L. Miller ~
MM O, bM ( 44c F se _ h _ -
DATE 2/24/98 ht=. ;t ,@- Dana W. Covdl l / DATE 3/2/98 i .
l 1
9807070141 900630 j PDR ADOCK 05000219 P PDR !
File: C1101-221-ES20413 xis 1 Tab. Calc l l 1 of 9 l
l ,
w______-_______-_-________________________ _ __ . _ _ - _ _ _ . .
DOCUMENT NO.
G U NUCLEAB C-1101-221-E520-013 TMI-I Reactor Vessel Welds Fluence, RT iqs and RTNDT per R.G.1.99 R-2, Pos. No.1 REV
SUMMARY
OF CHANGE APPROVAL DATE y NON SUBSTANTIVE changes. Editorial corrections / clarifications /
in Sections 1.0,2.0,4.2,4.3,5.0, and Table 1; pages 2,3, and 5. ~
G. ehmann 6/29/98 D. Covill 6/29/98 N0036 (6/98) 1a
EPU wucuram Calculation Sheet Subject. TMI.1 Reactor Vessel Wolds Fluence, RTris and Calc No Rev No Sheet No RTwot per R.G.1.99 R-2, Pos. No.1. C-1101221-ES20-013 1 2 of 9 l 1.0 Problem STATEMENT:
As a result of NRC GL 92-01, the NRC issued a close out letter regarding GPUN's response for TMI-1. The NRC letter concluded that GPUN's essessment for the 15 2 EFPY Tech. Spec. reactor vessel PU limrts, in using weldment irradiated surveillance capsule data. did not apply the chemistry rato procedure contained in R.G.1.99 R-2. Had GPUN apphed the rato procedure to the then available surveillance
, data, plus the additional TMi-2 surveillance capsule data whch subsequently became available, then, while the Crumistry Factor would have remained relattvely unchanged, the evaluated capsule data would have indcated that two (2) of the seven (7) values would have failed thC credibihty test. Fashng the credibiitty test prohibits reduction of the standard (c3) error associated with the shift in RTuor. This would resutt in a larger margin term (M) in the calculaton of the ARTNOT-GPUN argued that it was snappropnate to apply the rato procedure to surveillance capsules from different vessels, but made of the same
. weld wire heat. '
The NRC Sts# disagreed with GPUN's argument for not applying the rato procedure and concluded that the Tech Spec P/T curves and the LTOP hmits may be unconservative The purpose of this calculaton rs to reassess the TMI-1 reactor vessel ARTNDT values, for the present (15.2 EFPY) pered of applesbility of the P/T curves and LTOP hmrts, and the RT Pis v alues at the endef-heense (EOL) point.
This calculaton will assess the ARTuor and RTetson the basis of positon No 1 of R G.1.99 R 2.
\
GPUN will then utihre bounding values of ARTwot for the 15.2 EFPY pared, and will perform a fracture mechanics analysis to re-assess the 15.2 EFPY P/T curves and LTOP limits.
2.0
SUMMARY
OF RESULTS:
The results of this calculaton yielded the following ARTwor values at the end of the present plant operating fuel cycle (cycle # 12):
1/4T insde Surface ARTnoT = 200 dog F 3/4T Outsde Surface ARTN ot = 155 deg F Estimated values had been used to perform the fracture mechancs analysis, pror to the finakzaton of this calculaton.
The values whch had been used are:
1/4T Inside Surface ARTN ot = 214 deg F 3/4T Outside Surface ARTwot = 160 deg F
. These estimated values bound the end of cycle # 12 values, and also bound the end of cycle #13 values, and are therefore conservative bounding values for use in re-assessing the 15 2 EFPY P/T curves and LTOP hmits ,
Flie: C1101-221-ES20-013.xis M Tab Calc Mof 9
.r. a.
_ _ _ _ _ _ _ _ - _ _ - - _ - - - _ _ _ _ - _ . _ . _ _ . &&7
_ - - . - - - - - - . - - - - - - - - - - -= - - -
(%u mucmn Cricul ti:n Sheet
! Subject. TMI-1 Reactor Vessel Weids Fluence, RTPTS and Calc. No.
Rev No Sneet No.
i RTNDT per R.G.1.99 R-2. Pos. No.1. C-1101-221-E520-013 l 1 3 of 9 l if we were to examine the RTuoy et the end-of-hcense (EOL) penod, then the Rinoy values would be as follows.
l 1/4T Inside Surface ARTNDT = 237 deg F -
l 3/4T Outside Surface ARTNOT = 180 dog F l
s An engineenng mechanics assessment of the vessel P/T hmits at the EOL penod, on the basis of these RTuoi values will be made to determine the impact on the plant operating window The results of this calculation yielded the following RTPTsvalues at the EOL pened Longitudinal Wold SA-1526 RTPTs = 262 dog F Circumferential Weld WF 25 RTpTs = 268 deg F These resultant values are less than the acceptance screening hmits of 10CFR50 61 (PTS Rule) which are 270F and 300F for longitudinal l cnd circumferential weld, respectively. l I
10
REFERENCES:
3.1 NRC letter dated Oct. 8,1997 ;
32 NRC regulatory guide RG 1.99 R-2 i 3.3 GPUN calc. No C-1101-221-5300-011 Rev. O, dated 1/18/93, subject, *TMI-1 Reactor Vessel Wolds Fluence and RTuor per R.G 1.99 R-2, Pos. No.2, versus Time".
!- 34 BAW-2108 Rev.1, May,1992, B&W Owners Group Matenals Committee report.
- Fluence Tracking System".
4 0 ASSUMPTIONS:
4.1 Matonal emL;;-s ra damage is in accordance with NRC R.G.1.99 R-2 (Ref. 3.2).
4.2 The soeumed plant availabshty (93.5%)is bened on pook of the past few cycles. This is a very conservative l assumphon because of the very high achieved availability dunng the post few cycles, l 4.3 The previous nobon of a power upgrade of TMI-1 to 2772 Mwt will not take place, and if it does, then as part of the
! power upgrade assessment a reassessment of the vessel fluence will have to be made.
! 5.0 DESIGN INPUT:
t 5.1 The effective full power days for cycles No.1 thru 5 are contained in Ref. No. 3.3
- 5.2 The effective full power deys for cycles No. 6 thru 11 were obta;ned verbally from Nuclear Fuels group and confirmed by the approximate values contained in the STA reports on the day of the refuehng shutdown.
File: C1101-221-ES20 013.xis Tab: Calc 3 of 9 i
i~
l t
CPUmucmn Criculitian Sheet Subject TMI-1 Reactor Vessel Weeds Fluence, RTPTS and Calc. No
! RTNDT per R.G.1.99 R-2, Pos. No.1. Rev. No. Sheet No C 1101-221-ES20413 0 4 of 9
8.0 CALCULATION
Methods:
Tha methodology to be employed is p=fe-d with the following steps 1-Update the reactor vessel fluence values by ftxing the effective full power days (EFPD) for the completed operating cycle adjust the availability factor for the future cycles [See Table No.1) 2-Calculate the fluence factor (FF) values at the locations of interest (inside surface,1/4T and 3/4T), per the R.G.1.99 R-2 form bened on the updated fluence values. [See Table No.2]
3-Establish the chemistry factor (CF) from R.G.1.99 R-2 CF table for welds, based on the best estimate of the weldment %Cu and %Ni content 4- Calculate the respective ARTuor and RT v pts alues, based on the sum of the instal ARTNOT, the shift in ARTNor, and the margin term. [See Table No.3) .
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i l' Fb: C1101221-ES20413.xis Tab: Calc 4 of 9 i
l L--____________-___________-________
FPU
' uuc4Ep Criculation Sheet !
Subject TMi-1 Reactor Vessel Welds fluence, RTPTS and Calc. No Rev.No Sheet No l RTNDT per R.G.1.99 R-2, Pos. No.1. C-1101-221-E520413 1 5 of 9 l l
I TABLE No.1 TMI-1 PEAK FLUENCE HISTORY AND PREDICTION USING BWFC CORRELATION Avadabitrty Factor = 0 835
(
Power Upgrade: 1 =yes: 'O VESSEL FLUENCE (a)
END of END of per TIME CYCLE CYCLE TIME TIME CUM TIME VESSEL FLUX INTERVAL CUMULATIVE No (YEAR) (EFPD) (EFPY) (EFPY) (n/cm2-s) (n/cm2) (n/cm2) 0 1974 8 0 0 0 0 0 0 4 1976 1 1284 8 3 520 3 520 14E+10 )
1.6E +18 1.56E+18 i 4 1985 9 1284 8 3 520 3 520 14E+10 1.6E +18 1.56E +18 5 1986 8 302 4 0 828 4 348 1 SE+10 3 BE+17 194E +18 6 1988 5 421.2 1.152 5 501 9 4E+09 3 4E+17 2 28E+18 I 7 1990 474 7 1 299 6 799 8 SE+09 3 SE+17 2 63E+18 8 1991 8 5080 1 392 8.191 8 SE+09 3 7E+17 3 01E+18 9 1993 8 639 4 1 752 9 943 7 4E+09 41 E+17 3 42E +18 10 1995 8 660 3 1 809 11.752 8 OE+09 4 6E+17 3 87E+18 11 1997 8 683 0 1 871 13 623 8 OE+09 4 7E+17 4 34E+18 12 1999 8 682 6 1.870 {
15 493 8 OE+09 4 7E+17 4 81E+18 13 2001 8 682 6 1 870 17 363 8 OE+09 4 7E+17 5 29E+18 ]
14 2003 8 682 6 1.870 19 233 8 OE+09 4 7E+17 5. 76E +18 15 2005 8 682 6 1 870 21.103 l [
8 OE+09 4 7E+17 6 23E+18 t 16 2007.8 682 6 1 870 22 973 8 OE +09 4 7E+17 6 70E+18 17 2009 8 682 6 1.870 24 843 8 OE+09 4 7E+17 7.17E+18 18 2011 8 682 6 1 870 26 713 8 OE+09 4 7E+17 7 64E+18 19 2013 8 682 6 1.870 28 583 8 OE+09 4 7E+17 8.11E+10 20 2015 8 682 6 1.870 30 453 8 DE+09 4 7E+17 8 58E +18 21 2017.8 682 6 1 870 32 323 8 OE+09 4 7E+17 9 05E+18 22 2019 8 682 6 1 870 34 193 8 OE+09 4.7E +17 9 52E+18 23 2021 8 G82 6 1 870 36 063 8 OE+09 4 7E+17 9 99E+18 24 2023 8 682 6 1.870 37.933 8 OE+09 4 7E+17 1.05E+19 25 2025 8 682 6 1 870 39 803 8 OE+09 4 7E+17 1.09E+19 26 2027 8 682 6 1 870 41 673 8 OE+09 4.7E+17 1.14E+19 27 2029 8 682 6 1 870 43 543 8 OE+09 4 7E+17 1 19E+19 28 2031.8 682 6 1.870 45 413 8 OE+09 4 7E+17 1.23E+19 j 29 2033 8 682 6 1870 47.283 8 OE+09 4.7E+17 1.28E+19 '
30 2035 8 682 6 1 870 49 153 8 OE+09 4.7E +17 1.33E +19 31 2037 8 682 6 1.870 51.023 8 OE+09 4.7E +17 1.38E+19 32 2039 8 682 6 1 870 52 893 8 OE+09 4 7E+17 142E +19 33 2041 8 682 6 1 870 54 763 8 OE+09 4 7E+17 l 147E+19 13 18 hw16 17.700 5.37E+18 1910 2014 28 77 816E+18 EOL l 11.84 1999 4865 15 20 4.74E+18 '
(a) Based on BAW-2108 Rev.1, May.1992 t
- File: C1101-221-ES20013.xis Tab. Calc 5 of 9
-_ _ _ _ _ _-. _ - - - - - - = - - - --- - - - -- - - - -
1 Gau aruc m n Subject. TMI-1 Reactor Vessel Welds Fluence, RTPTS andCalculation Calc. No Sheet _
Rev. No Sheet No. )
RTNDT per R.G.1.99 R-2, Pos. No.1. C-1101-221-E520-013 0 6 of 9 TABLE No. 2 TMl-1 Reactor Vessel Weld F9_we Availabihty Factor = f @ %TW = Fluence
- e^[-0 24*8 4375*(%TW)]
0.935 Inside Surface 1/4T Location 3/4T Location CYCLE CALENDAR CUM TIME Wold ID Weld ID Wold ID No YEAR (EFPY) SA-1526 WF-25 SA-1526 WF 25 SA-1526 WF-25 0 1974 8 0 000 0 0 0 0 0 0 4 1978 1 3 520 141 E+18 150E+18 8 49E+17 9 03E+17 3 08E+17 3 28E+17 4 19859 3.520 141 E +18 1.50E +18 8 49E+17 9 03E+17 3 08E+17 3 28E+17 5 1986 8 4 348 1.75E+18 187E+18 1.06E+18 1.12E+18 3 84E+17 4 09E+17 6 1988 5 5 501 2 05E+18 219E+18 1.23E+18 1.32E +18 4 48E+17 4 80E+17 7 1990 6 799 2 34E +18 2 53E+18 141E+18 152E+18 513E+17 554E+17 8 1991.8 8191 2 66E+18 2 89E+18 160E+18 174E +18 5 83E+17 6 32E+17 9 1993 8 9 943 3 01E+18 3.28E+18 1.82E+18 198E+18 6 60E+17 7.1BE +17 10 1995 8 11 752 3 40E+18 3 '/2E+18 2 05E+18 2 24E+18 7 45E+17 814E+17 11 1997.8 13 623 3 80E+18 4.17E +18 2.29E +18 2 51 E+18 8 33E+17 913E+17 12 1999 8 15 493 4 21E+18 4 62E+18 2 54E+18 2 79E+18 9 21 E+17 101E+18 13 2001.8 17.363 4 61E+18 5 07E+18 2.78E+18 3 06E+18 1.01 E+18 1.11 E+18 14 2003 8 19 233 5 01E418 5 53E+18 3 02E+18 3 33E+18 1.10E+18 121 E+18 15 2005 8 21.103 5 41 E+18 5 98E+18 3 26E+18 3 60E+18 1.19E +18 - 1.31 E+18 16 2007.8 22 973 5 82E+18 643E+18 3 51E+18 3 88E+18 1.27E+18 141E+18 17 2009 8 24 843 622E+18 6 88E+18 3 75E+18 415E+18 1.36E+18 151 E+18 18 2011 8 26 713 6 62E+18 7 33E+18 3 99E+18 4 42E+18 1.45E+18 161E+18 19 2013 8 28 583 7 02E+18 7.79E+18 4 23E+18 4 69E+18 1.54E+18 1.71 E +18 20 2015 8 30 453 7.43E+18 8 24E+18 4 48E+18 4 97E+18 1.63E +18 1.80E+18 21 2017.8 32 323 7 83E+18 8 69E+18 4. 72E +18 5 24E+18 171 E +18 1.90E+18 22 2019 8 34.193 823E+18 914E+18 4 96E+18 5 51E+18 1.80E+18 2 00E+18 23 2021.8 36 063 8 63E+18 9 59E+18 S.20E+18 5.78E+18 1.89E+18 2.10E+18 24 2023 8 37.933 903E+18 1.00E+19 545E+18 606E+18 1.98E+18 2 20E+18 25 20258 39 803 9 44E +18 105E+19 569E+18 6 33E+18 2 07E+18 2.30E+18 26 2027.8 41.673 9 84E+18 1.10E+19 5 93E+18 6 60E+18 215E +18 2 40E+18 27 2029 8 43 543 1.02E+19 1.14E+19 617E+18 6 87E+18 2.24E+18 2.50E +18 28 2031.8 45 413 1.06E+19 1.19E+ 19 6 42E+18 7.15E+18 2.33E +18 2.60E+18 29 2033 8 47.283 1.10E +19 123E+19 6 66E+18 7 42E+18 2 42E+18 2.70E+18 30 20358 49 153 1.14E+19 1.26E+19 0 90E+18 7.69E+18 2 51E+18 2 79E+18 31 2037 8 51.023 1.19E +19 1.32E+19 714E+18 7 96E+18 i
2 60E+18 2.89E+18 32 2039 8 52 893 1.23E +19 1.37E+19 7.39E+18 8 24E+18 2 68E+18 2 99E+18 33 2041.8 54.763 127E+10 1.41 E +19 7.63E+18 8 51E+18 2.77E+18 3 09E+18 13.2 2002.16 17.700 4 68E+18 5.16E +18 2.82E+18 311E+18 1.03E+18 1.13E+16 EOL 2014 28.770 7.06E +18 7.83E+18 4 26E+18 4 72E+18 1.55E+18 1.72E+18 11.84325 1999 4865 15 200 414E+18 4 55E+18 2 50E+18 2.74E+18 9 07E+17 9 97E+17 j l
Wold Location Fluence Correction Factors , BAW-2108 Rev.1. Table No 5 i WELD 10 F (anmuth) F (axial) F (radia!) F (total)
SA-1526 0 94 0 96 1 0 902 Cyc 1-5 SA-1526 0 89 0 96 1 0854 Cyc 6 & plus WF-25 1 0 96 i 1 0960 l
l l- fue: C1101-221-ES20-013.xis l . Tab. Cale - 6 of 9 4 I
E_-_-_____ N _ _ __ _ _ .
i i
meu muern, Calculation Sheet
Subject:
TMi-1 Reactor Vessel Wolds Fluence, RTPTS and Caic. No.
f RTNDT per R.G.1.99 R-2, Pos. No.1. Rev No Sheet No C-1101221-E520-013 0 7 of 9 i
l TABLE No. 3 TMI-1 Reactor Vessel Welds RTen & RTum per R.G.1.99 Rev. 2. Pos. No.1 Avadabihty Factor = 0 935 Inside Surface 1/4T Location 3/4T Loc,at>on CYCLE CALENDAR CUM TIME Weld ID Weld ID Weld ID No YEAR (EFPY) SA-1526 WF-25 SA-1526 WF-25 SA-1526 WF-25 0 1974 8 0 00 63 63 63 63 63 63 4 19761 3.52 170 173 147 150 112 114 4 19859 3 52 170 173 147 150 112 114 5 1986 8 4.35 181 184 157 180 118 120 6 19885 5 50 189 193 164 167 123 126 7 1990 6 80 197 201 170 174 128 131 8 1991.8 8 19 204 208 177 181 133 136 9 1993 8 9 94 211 215 183 188 137 141 10 1995 8 11.75 218 223 189 194 142 146 11 1997.8 13 62 224 230 195 200- 147 151 12 1999 8 15 49 230 236 201 206 151 155 13 2001.8 17.36 236 241 206 211 155 159 14 2003 8 19 23 241 24'7 211 216 159 163 15 2005 8 21.10 245 251 215 221 162 167 16 2007.8 22 97 250 256 219 225 166 170 17 2009 8 24 84 254 260 223 229 169 174 18 20118 26 71 258 264 -227 233 172 177 19 2013 8 28.58 261 268 230 237 175 180 20 2015 8 30 45 265 271 234 240 177 183 21 2017.8 32 32 268 't74 237 243 180 186 22 2019 8 34.19 271 278 240 246 183 188 23 20218 38 06 274 281 '243 249 185 191 24 2023 8 37.93 277 263 246 {
252 188 193 25 2025 8 39 80 -280 286 248 J 255 190 196 26 2027.8 41.67 282 289 251 257 192 198 27 2029 8 43.54 285 291 253 260 194 200 28 2031.8 45 41 287 294 256 262 196 202 29 2033 8 47.28 289 296 258 265 198 204 30 2035 8 49.15 291 298 260 267 200 206 31 2037.8 51.02 l 294 300 262 269 202 208 j 32 2039 8 52.89 296 302 264 271 204 210 j 33 2041.8 54.76 298 304 266 273 206 212 '
- No YEAR (EFPY) SA-1526 WF-25 SA-1526 WF-25 SA-1526 WF-25 13.2 2002 16 17.70 236 242 207 212 156 160 EOL 2014 28.77 262 268 231 237 175 180 11.84325 1999 4865 15.20 229- 235 200 205 150 154 l
- initial Chemistry l WELD ID RTndt MarDin Factor SA-1526 -7 69 5 220 6 values from Ref. No. 3.1 WF-25 7 69 5 220 6 i
- File C1101-221-ES20 Ot3.xis Tatr Calc 7 of 9
Shast 8 of 9 C-1101-221-E520-013 NUCLEAR VERIFICATION PLAN /
SUMMARY
SHEET (EP-006)
Scope of Verifcabon erify input, assumptions, methods, and results are accurate and reasonable.
l Item No, Method / Depth of Verification Required Reg'd Compt. Date l 1 Verify inputs are accurate and appropriate. z. 2 ,..Yd 2 berify assumptions are adequate.
3 Verify methods appropriately used.
4 Md Verify results are reasonable.
Assigned Vertricotson Engineer R. L. Miller oualified per 4.4.1.3.b O Yes $ Waived JustifcahonforWolver PM6tz-i6oe.-e:p soi7ef 77h> sus M cr Sechon Manager (SM)(sign) !
j Date 32.95 Summary of verification scope, methods, results and conclusions.
TMI Reactor Vessel Vertecation
- 1) Checked references to verify A) RT, anno of welds SA-1526 and %7-25. B) coppcr and nickel content of welds WF-25 and SA 1526 and C) estimated cunnlative peak fluence value for end of Cycle 12 (15.5 EFPY) and end of hfe (28.8 EFPY).
- 2) Verified curnulative EFPY and calendar date for end of cycle 12 and end oflife via conversation with OPUN Fuels Group.
' 3) Ceafinned fluence value as welds 47-25 and SA-1526 at end of cycle 12 and end oflife using equation provide in BAW 2108 Rev.t.
- 4) t'aladatad ARTierr for welds SA 1526 and %7-25 at and of cycle 12 using equations provide in NRC Regulatory Guide 1.99 Rev.2 Position 1.
l
- 5) Calculated RTm for welds S A 1526 and 47-25 at end oflife using equations provided by 10CFR 50.61 Conclusion
- 1) ART,an results for welds SA 1526 and WF-25 at end of cyc1412 and end oflife are reasonable and acceptable. RTm results for welds ,
SA 1526 and WF-25 at end of hfe are also reasonable and acceptable.
BIsed on this evaluation, the calculation is verified to be acceptable.
Vertficauon Engneer (print) g g g g/ ( g/[' (ssgn) / $ Date((gg f
F 03 02 '98 11:39 ID:GPUfJ CHEM %TLS. LABS, FAX:1-610-375-5820 PME 2 NUCLEAR CALCULATION per.VER!FICATION rp4os; CHECKLIST mot 9 ' of 9 case. %ue 7:n y y a m c 4,-
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les son by. (Print Name) G s:PrA2 .de A+ . / 6 // W :22/- D J ty)y novc7 AA/ / A A-
_mp Section time o e check merk to lhe opputable bos (Yes. No, NA) for eash leem *
%..h .Date,d W p -
"NO"sesy ledirese the design er tevitrattanla tarempbste regering a teak ergeant be mustgeed by th N hert6ne Menes r ehes maew each "NO* respener se deserence e respnenible herthaif rs . Teek Msgmeet mesde s Maanger l
-N/A*(het Apparable)does out roepdes may hert6mr enema by the Vertnrenne Eartrar.
Thr appropewpttele VerlArnetum Hausenery by the terinroe6*n Emedeerr. (Yh)(Eddhit 'lAn sesy he seed to outume the veetAresian EmeteeWe wor
. orcases rets derseed
_ Review Check,,
ITEM 8 Desean Compliance _
w- a-a A bem - Were the inputo Correctly selected tederenced (tel Yes l No N/A ,
colonnehon? ,
eet rowsion) and incorporated into the
] ]
Aamumentans - Are assumpoono necessary to perlorm the colpulation ee adequetely descr6tted and reason
_ ]
e40ence, property 6 dent: fled and their requremente rnet?Ranulatory ue and Ranulf amante - Ate the app
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ease..~
- .~ .- see awa.a t,uel on and o,e.enn, e enene. t. con cone e,e*
O OM b ~~sev. in. osewniertees %e.,n.nie oe.n sei.ne" O
Methaste -Wee en appropriate cakxilet60n nwthod used?
Onanut - la the output reasonstile compared to inputo' O O l Aasinutanas design toqueromente have boon seltelectority accomphahed?
CrMane - Are the . , _ A grtsne incorporated in the calculeDon suff6clent to allow venAcetion tha
] ] g hadaanaq Eamesurg - Has the ceiculation paperty conendered radiaten exposure to the puhec and plant perso -
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