ML071580375
| ML071580375 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/22/2004 |
| From: | Gardner S, Heffner J Nuclear Engineering Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NMPAST-01-001, NMPAST-02-001 H21C076, Rev 00 | |
| Download: ML071580375 (106) | |
Text
Nine Mile Point Unit 2 Alternative Source Term Calculation H21C076 "X/Qs for Releases from NMP Units 1 & 2 (CNS Calcs NMPAST-01-001
& NMPAST-02-001)"
Project: NINE MILE POINT NUCLEAR STATION Unit(1i, 2.orO=Both) : 0i i
bisciphneý:
ANALYSis' Title T...
"alculatonNo X/QS FOR RELEASES FROM'NMP UNITS 1 &,2 (CNS CALCS H21 07on NMPASt01-011 & NMPAST2-1)
(Sub)syem(s)uildng Floor Elev.
Index*No.
I N/A:
N/A kNA N/A 0riginator(s)
'JAMES HEFFNER (C571:33)!/ HANE:GARDNER (C57133)
Reviewer(s),t/Approver(s)
I S GARDNER (0571133), J HEFFNER- (G57133)./T NEIDER: GNS). SEE REMARKS:
GLENN STINSON - NMPNS EvalI.i DER' r Prep'dc Reviewed Rev Description ChangeBNo.
y Date,.
IBy Date-Apo Date
- 001 ORIGINAL ISSUE N/A Clomputer 0utpu~ticrofilm Filed Separately (Yes INo I NA):NO Safety Class (SRt/NSR./Qxx) : SR Superseded: Oocument(),:.NONE, Document-'Croass Reference(s) -Fdor additinIal ref*rences see;page(s):SEE PAGES:29, 78,79 & 97
- Flat,
'Doc No
__Document No_.....
Type Index Sheet Rev.
General Reference(s):
SEE: PAGES:29,78,79 & 97 Remarks':
Cr15 CALCULATION ýNMPAST-0l-OO1 CALCULATES X/Qs AT THE-EAB & LPZ,(SEE PAGES 3 THRU 50)
ýCkl CALCULATION, NMPAST-0C2-001 CALCULATES XI0s FOR: CONTROL:ROOMS.& TSC,(SEE PAGES 51 THRU 90)
THESE CALCULATIONS WERE:INDEPENDENTLY REVIEWED, AND VERIFIED:IN ACCORDANCE WITH: NEP-DES407, BY
.NYSIS CORP -(NI 3617) (SEE PAGES 91 THRU 1.06),
- NOTE: PAGES23,24 &$
CONTAIN
.COLOR PRINTING. NO INFORMATION, IS OST IN BLACK & WHITE.
,Confirmation Required.(YesI No): No FinalIssue Status:
Turnover Required Se Pges)
_________APP (YsBI N/A).:WNA 1.CFR5O..9 Evaluation Number(s):.N/A Component ID(s) (As.shown*.n MEL):
Copy of Applicability Determination or 50.59.Screen N/A Attached? Y'es E] No [3 Key Words': XfQP:ATMOSPHERICDISPERSION, EAB, LPZ, CO.NTROL ROOM, TSC, PAVAN, ARCONOB
\\\\NAS-NMP-O1\\E48425\\Ul1CALCs\\CaIO76\\H21 CO76Cov~doc NPDS0
.NEP-DES-v Rev 06
Calculation Cover Sheet Calculation.No, NM, AST-014001 Rw.. 2
-No. ofPagcs 45 Title Calculationof X/Os at theEAB 'and LPZ fromReleases at NMPUnits J: and 2 Riv..O Name Signature Dt Prepare 5y Jamnes Hefffhr___
,CheekedBy Shane Gardner ApprovedlBy
.TaraNeider Rev.AI Name Signature at PrePared By James Heffner Checked By.
Shane Oardner Approved By TaraNider Description of Changes.
- Ncw. meteorolgical,(ME-T):data is incorporated.
6 Rounding errors contributed torminor discrepancies inrcsuldtsof, NMPAST-Ol-00.,
uo, All, calculatdonrzswere rerun :inPAVAN using new iMET data.
- The WSW is regarded as a land rather than coastal spetor for NM? Unit 2Jin this, revision:.
o Main Stack distance to EAB was changed from 405 rento 1,615 m.
o Combined Radwaste/Reactor Building'Ventwas changed from 747m to 1,381 mn.
Eliminated coastal sector distances, to EA, o.W, WNW,NW, NNW., N, NNE,NE, and ENE sectors are considered, coastal and are not conrsidered for evaluation in this revision.
o Coastal sector distances to'EAB were substituted with the minimum land sector distances to obtain overall site. X/Q values.-
Pr6vided additional calculations for stack releases in each sector to prove that maximum X/Q concentrations do not occur at distancesibeyond the EAB and LPZ.
o: RG 1.145 Rev. I mentions that X/Q values may,,occur atdistances beyond theEAB and LPZ.
o PAVAN runs were performedat various distances ranging from 100 -
9,000 m for. stack releases to prove that maximum X/Qs exist at the EAB and LPZ.
Affected Pages:- Sections 5:tlroueh,9.
Na~oc~74-4'4 (4.
'Rev.:2.
Name VSigna~ture Dt Pe, dBy iShane Gardner 1./Iq,/Ps Checlcr By Dvid,Match k Apprioved BY Larry Smith_
A V
~
Description of Chaages
/
The purpose of this revision is to respond to comments imade in athird.party review performed by NISYS
- Corp. at thereque.ofNMPNS. Several comments were made and th-reader is referred to the NISYS
,documentiS - 1169-DVOOI/R0 for more detail CNS, andNMPNS agreed to'a planto resolve a selection of the NISYS conmments (seCNS-03-2 I. 9/24/03 and electronic tortespondence from.Timothy M. Kurtto ShanerGardner. November.6.2003, "Re: CNSComments on NISYS ReviOewof XJQ Calculations"). CNS-03722 18provides a description regarding how the comments were addressed and providesthe basis for incorporating thecomments:into thiscalculatior. More spcifically;the following comaments were addressed:
.NISYS
- Comment, No*
Description AffecmedPage(s) lb imclude a scale dravwing (c6mpass "rose")
Appendix A I c statement documenting conformance toSafety Guide23 3-4, 24 (Ref. 21) 2a justifration.ofPAVAN variable "A'i(building wakearea) 6,24,:(Refrs. j9&20) 3b correctn and review of28 hatnd-checked 0.5% X/Qvalues.16-17i, 19-22,,
3c' p:ovide a basis for intermediate time.pointss
ý17
ý5a ad:adae
,ailed isting offiles on CD be provided Appendix C Resolution ofNISYS comment3b resulted in minor changes tothe results provided insection?. More specifically, it washdetemined Ithat PAVAN outputs were correctly processed internally to the 6ode (1Ný VLOP rouine) and therefore theresilts; intheoutput files were correc. leresults tables inhsection 7
,were updated toreflect this finding. The -ew results w.erc only sligbtly-different fiom the results.o*
previous revisin..1.
hiaddition tothe'changees.indicated above, the calculation was turther revised to incorporate
.nnor editorial changes Affected Pages: Calculation Cover. Sheet,(Titl_ 1 all pages: therafIter CNS O QForm: 6A-3.2. Rev. 0
Calculation. Review 'Checklist Corec cacuaton fomat.:..,:.;;:..;
Calculation...,
- , W,.,,.*.:l}.,,........
- v. #____
-Circle. as, auprolrate, die yes/NONA for all itj Correct-caculation o
rmpai
...........,,..........;.......61:tb/NA
'Correctness of assumpions................................I................
A....
Adqucyofasumtin ass.......
/M Correctniss of pqrameters used...............
o.NA Appropriate choiceýof method o/NA Adequate documentation of method..............
.No/NA
'Correct applcation ofmethod o/NA C orre tnes s......
ro A
Adequate Reference list..........
0o/NA If computer:software was -used to perform the calculation, the followng elements shall.
.also be considered:
Proper. softare veritication and verification documentation...........................
jYNo/NA Correctness of input parameters....................................
ý No/NA Correct information in analysis calculation o/NA Correct interpretation of :rsults:...
1.,,,....wqNo/NA Sig"nue
______Date CNSWQA Form: QA-322;2 Rev. 0
.on.elatonCalculation No:,-NMPAST-01.-001 Cons ellaion Rev.'2 Nuclear Services Date: Dec. 19
.2003 Table oftContents
.Objectve................
- 2. ;Background........................................................................................................................
1 2.1. Applicable Regulations and Commitments.3...........................................
,................... 3
- 3. Methodology......
....................... 4
- 4. Computer HardwarelSoftware Usage...........................................................................
5 4.1. Hardware Used........................................................................................................
5 4.2. Software Used..................................................
- 5. Inputs and Assumptions..................................................................................................
.54 5.1. Design Input 5
5.2. Assumptions................................
............................................................................ 6 5.2.1. ReleaseI Pint Distances to. thel: AB and LPZ.....
6 5.2.2. Building Wake Correction Factors..............................
6 5.2.3. S ite Topography........................................
6.................
......... 6
'5.2.4. Identical Data....................
7 5.2.5. Maximum Category 12:Wind:Speed..........................................................
........... 7 5.2.6. NMP Unit 2 WSW Sector....
....... 7 5.2.7. Coastal Sectors.........
7
- 6. Calculation and Results....
........................... 15 6.1. Determination of Distances for Calculations.....
15 6.2. ENVLOP Programming Error..................................................................................
16 6.3. ENVLOP Error_..................
.... 17 6.4. Results............................................................................................................
17 7.,Conclusions I.... '......
22
- 8. References.....................................................
- ..24 Appendicess...................................................
t................................................
5 Appendix A - Figures: EAB and LPZ Regions Showing Associated XQ; Directions......... 26 Appendix B - PAVAN Output....................................
29 Appendix C - Listing of Files on DATA CD-ROM for Calculation NMPAST-01 -ý00...... 42 Page 1 of 45
GoC te ti
""C-Calculation No: NMPAST-01 -001 Reiv62 Nuclear Se ices Date:Dec. 19, 2003 List of Tables Table 5.1-4.a PAVAN Input for'Unitf -Main Stack Release.........
8 Table 5.11 -. b PAVAN Input for Unit I Reactor Building Blowout Panel Release.,.....
9 Table5.1-1.c PAVAN Input for U nit2 Main Stack Release.............................................
10 Table,5.1 -1..d PAVAN Input for'Unit2 Combined Radwasteand Reactor Building Vent Release..........
12 Tablea 5.1-2ICard 9 Input................................
.13 Table 5.2-1 Input References forSimilar PAVAN Input Files...
........................... 15 Table6.4-1 Nine Mile Point 0.5%, Sector Dependent Short-Term X/Qs Calculated with PAVAN...........................................................................
19 Table 6.4-2-Unit 1 Main Stack Non-Fumigation X/Q Values.;....................................... 20 Table 6.4,3 UnitfI Reactor Building Blowout Panel X/Q Values....................................
20 Table 6.44 Unit.2 Main Stack Non-Fumigation X/Q Values........
21 Table 6.4-5 Unit 2 Combined Radwaste/Reactor Building Vent X/Q Values................ 22 Table 7-1 Ground-Level Release X/Qs Selected for Evaluation at NMP.....
I............ 23 Table.7-2.Elevated Release X/Q Selected for Evaluation at NMP......,..
23 List ofFigqures Figure 6.1-1 Unit I Main Stack X/QVersus Distance...........................
18 Figure 6.1-2 Unit 2 Main Stack X/Q Versus Distance................................
FigureA-1 EAB and Associated X/Q Directions..............
I
........... v27 FigUre A-2 LPZ and Associated X/QDirections....
............... 28 Page 2 of 45
Calculation No: NMPAST-0101' Consi t.elatio Rev. 2 NuclearS,*ervics Date: Dec. 19,2003
- 1. Objective Theq purpose of this calculation isto determineconservativeestimates ofexclusion area, boundary (EAB) and low population zone.(LPZ) atmospheric dispersion coefficients (XIQs)for use inacalculations which determine'radiation dose consequences associated with; postulated design basis accidents occurring :at Nine Mile Point Nuclear ;Station,(NMP) Unit '1 and Unit,2.
2.Baickg roun d NMP has requested the services of Constellation Nuclear SerVices.(CNS)to evaluate and Update offsite and Control room atmospheric dispersion coefficients'for both Units 1 and 2.
The atmospheric dispersion coefficients are needed for a scoping study to determine the feasibility of the Use 'of the Alternative Source Term (AST) methodology for the determination oftdesign basis accident dose consequences and can be applied'to other calculations which
,determine radiation dose bonsequences, at the EAB ':and LPZ boundaries.
Afterawpostulated accident at the NMP Unit 1 or Unit 2, radioactivity may reach the
,atmosphere by Several pathways. These pathways include the reactor building blowout panelo the turbine bUilding blowout panel and the mainrstack for Unit 1.For Unit 2, the release,
.pathways iniclude-the combined radwaste. andireactor building vent,,the main steam tunnel,.the standby gas treatment 'system building, the post accident sampling system panel and the main stack. Once the'radioactivity reaches the.atmosphere, it will: create dose consequences atthe EAB and the outer boundary of the LPZ. The determination of atmosphenc dispersion coefficients provide the amount of radioactivity reaching the EAB and LPZ for a given source for use in the dose consequence determination.
This calculation provides conservative estimates of atmospheric dispersion coefficients at the
,EAB and.LPZ 'from the following release sources:
- Unit I Main Stack
- UnitI Reactor Building Blowout Panel
- Unit 1 TurbineBuilding BlowoLut Panel
- Unit 2 Main Stack
- Unit 2 Combined Radwaste and Reactor Building Vent
- Unit 2 Main Steam Tunnel
- Unit 2 Standby Gas Treatment System Building
- Unit`2 Post.Accident Sampling System Panel 2.11. Applicable Regulations and Commitments PAVAN is used to determine X/Q values used in the assessment of dose consequences of
,design basisaccidents in nuclear power stations. 10 1CFR Part 100 (Reference 6) and 10CER Part50 '(Reference 7) require such assessments. PAVAN follows the guidance of R.G. 1.145 (Reference 2) for calculating X/Qs. Meteorological data~arebhourly averages obtained from Page 3 of 45
"Calculation No: NMPAST-01o001 Nulearteruices.
Rev. 2 Nucle(arSer.vices Date: Dec. 19, 2003 NMP Joint Frequency Distribution Report.(JFD) (Referenceg) and: the analysis conforms to orequirementsof R.G. 1.145 (Reference 2 )-and R.G. 1.23 (Reference 21).
- 3. Methodology The PAVAN program uses meteorological data in the form of joint'frequency distributions of hourly averages of wind direction and wind speed by atmosphenrc stability class. Wind direction is distributed into 1:6 sectors. For each sectora 0.5% X/Q is calcUlated :to represent theO -2 'hourX/Q 'in accordance with R.G. 1.145 (Reference2). The 0.5% X/Q "is the value which is equaled or exceeded 0.5%,of the'time. PAVAN also :calculates.a sector annual average X/Q. in accordance with R.G. 1 111 (
3 TheD 0-2 hourX/Q value and the annual average X/Q are used to determine:.sector X/Q values. for-various intermediate time,.
periods.
In a similar manner, PAVAN also calculates~a 5% overall site X/Q value that is independent of wind.direction. :This is:the site value that is not exceeded more-than 5% of the time, and is iusedto represent the o -.2'hour X/Q. The overall site annual average X/Q is calculated in accordance with R.G. 1.111 (Reference 3). The 0-2"hour X/Q Value and theannual average X/Q9are used to deotermine overall site X/Q values for various intermediate time periods.
In addition, PAVAN also calculates short-term sector fumigation X/Qs for both the EAB and LPZ in accordance with R.G. 1.145 (Reference 2),for stack releases. For each sector, :the.
larger of the sector fumigation and the sector non-fumigation X/Q should be used for theO - 2;
'hur.time period.,
The highest X/Qvaluefor the 1.6 sectors represents the maximum sector X/Q.
'The X/Q-value forEAB or LPZ evaiuations should be themaximum sectorX/Q or the 5%
overall site X/Q, whichever is.higher. A more detailed description on the methodology used;by PAVAN tocalculate XIQs is provided in the reference documentation (References 2,:3 and.8).
Page 4 of 45
CalulaionNo:NMPAST-O01-OO1 L
- Rev. 2.
N'uclear Serices Date: Dec. 19,2003
- 4. Computer HardwarelSoftware Usage 4.1,.,Hardware Used All PAVAN X/Q calculations were performed on PC CNS-76, operating under the Windows 98 operating system. PAVAN has been previously verified on CNS-76min accordance with the CNS QA Program (Reference 15).
4,2. Software Used The program PAVAN is written in FORTRAN IV computerlanguage and is compatiblewith a CDC 7600 computer system under the NOS 1.0 Operating system. A further description of PAVAN is included -in the user's guide.(Reference 8).
Microsoft Excel wasalso used for calculatiron.purposes outlined in Sections 5.2.3, 6.1 ý,and 6.2. In accordance with the. CNS QA Program (Reference 1), no computer code verification is required for Excel.
- 5. Inputs andAAssumptions 5.1. Design Input Table 5 1-1 summarizes the design input used to generate the input filesfor the PAVAN calculations. The actual input files for PAVAN are included in the Input'Files folder on the enclosed CD,. Specific inputs for the meteorological data (Card 9):of the PAVAN input file are
'indicated in Table 5.1-2. The meteorological data was obtained from the-NMP Joint Frequency Distribution Report (JFD),(Reference 9) and appears in the Revised NMP 60m JFD 1997-2001 for CNSfile on the enclosed CD. Complete descriptions and proper formats of each data
,.input is included in the PAVAN usees guide (Reference 8). No tables are provided.for'the
..following calculations:
- Unit 1 Turbine Building Blowout Panel A Unit 2 Main:,Steam Tunnel Unit,2 Standby Gas Treatment System Building:
o Unit.2 Sampling System. Panel The reason for.the omission of these tables. is explained inSection 5.2.4.1 The design inputs required for calculating the, off-site X/Qs u.using PAVAN were obtained from
,the following documents:
4 Accident X/Q Values for Nine Mile Point Unit '1 Releases from the Main Stack and the Reactoraand Turbine Buildings (Reference 10)
Page 5 of 45
Calculation No: NMPAST-O1*-001 Rev..2 Nuclear Services Date: Dec., 19,2003 Technical Support Document Nine Mile Point Unit 2 Accident and Long -Term Diffusion
!Estimates and the Methodology Used in their Calculation (Reference 11)
NMP DrawingC0-26658-C (Reference 12)
. NMP Joint Frequency Distribution Report (JFD) (Reference 9)
- NMP Unit 2 USAR Figures 2.3-43 through 2.3-46 (Reference 13)
- NMP Drawing-C-18713-C (Referehce 16)
SNMP Unit 2USAR Figure 1.2-11 (Reference 17) 5.2. Assumptions 5.2.1. Release PointDistances tothe EAB and LPZ Due to the close proximity of the Unit I reactor building blowout panel with the turbine building blowout panel, identical distances to the EAB and LPZ were used for each ofthese release points.
Due to the close proximities of the Unitl2 combined radwaste and reactor building vent, the
.main stearm tunnel,, the stand by. gas treatment system building and the post accident sampling system panel, identical distances to the EAB and LPZ were used for eacdhof these release
- points.
5.2.2. Building Wake Correction Factors For the cases involving groundlevel releases,, the-smallest vertical-plane cross-sectional area of the corresponding reactor building, i*n 2, was used in accordance with:R.G. 1.145
'(Reference 2). An area of 2,082 m2 was used (References 1:0, 1,9 and 20) for, the Unit 1 releases classified as ground level, and an area of 2844 m 2 was:used:(Reference 14)-for the
.Unit 2 releases classified as ground level.
5.2.3. Site Topography For both Units' main stack releases, distances of 3,000 m and 6,000 m were selected for input as distanceswith terrain data for each sector. Two distances were selected to provide sufficient description of how terrain, height varies around the entire site. 6,000 m Was.selected since it representsroughly the entire distancefrom the stack releases tothe LPZ. 3,000 m was'selected since-it represents roughly half of the:distance::from the stack releases to the
.LPZ. Terrain heights for all 16 sectors were provided in Reference 13 at various distances
'foro the site. A straight-line slope was assumed to exist between the terrain height at the Site and :the terrain heightat various distances fromrthe site. The straight line slopes were used in Microsoft. Excel to estimate the.terrain heights at 3,000o m and '6,000 m. For any terrain height calculated as less than plant gradeelevation, a terrain height of zero meters was assumed, since-the height above plant grade level is called forin the PAVAN user s guide Page 6 of 45
Calculation No: NMPAST-01-001
'~PON3E~LJhPU.
ev. 2 Nuclear Services Date:` Dec. 19,2003 (Reference 8). This entire. terrain heightcalculation, and the associated files, are included in the Terrain Height Estimates file:on the enclosed CD.
-Since there -are no severe terrain features such as deep valleys or mountains,.in the vicinity of NMPR.to affect the diffusion, of radionuclides releases from the *elevated main stacks, the default terrain adjustment factors.(TAF=l) were applied..
5.24., Identical Data For the reasons mentioned in Sections 5.2.1* and 5.2.2, several of the PAVAN inputfiles, with the ex ception of file name, have the same inputdata and assumptions. For this reason, several of these files are omitted from Table 5.1-1. Input reference files identical to these
.omitted input files are providedin Table: 5.2-1. Likewise, the output files for those.mentioned in Table 5.2-1 are alSo assumed Io be identical to their reference output files and are therefore not included in this report. These files, bothinput and output, are: however contained in the respective InpUt Files or Output:Files folders. on the enclosed CD.
5.2.5. Maximum Category 12 Wind Speed Since the NMP meteorological data (Reference 9) fails to provide a maximum wind speed for category 12 winds, a conservative value of 60.5 m/s was selected., Maxmum Wind speed is required. input for each wind category!in PAVAN.
5.2.6. NMP Unit 2 WSW Sector The NMP Unit 2WSW sectordistance tob;theEAB maybe considered as.a land or: castal distance (Reference 11). This calculation uses land distances to the EAB from the Main Stack and Combined Radwaste/Reactor Building of 1A,615 m and 1.,381 m, respectively.
- 5.27. Coastal Sectors The folloWingsectors are regarded as coastal and are not considered.(Reference 18):
oW
- WNW
- NW
.NNW oN
- NNE oNE.
ENE Page 7 of 45
Lc4~74-~N' Nuclear Services Calculation :No: NMPAST-1-001 Rev.2 Date: Dec 1:9, 2003 Because PAVAN requires distance data for 16-sectors in order to calculate X/Q values, minimum land distances were substituted for coastal distances. The land distances substituted for the coastal sectors along with their reasoning are included in Table 5.1, Table 5.1-1.a PAVAN lnputfor Unit 1 Main Stack.:Release Card Variable Data Input Type Name 1*
KOPT(1,4, 6, 0.
8 ),,.
- KOPT(7,9-I::
10)..
2 TITLD(1-5)
Nine Mile Point, TITL(6-10);
1/01/97--to 12/31/01
- TITLD(11,15)
Elevated 106.7 meters 3
TITLDO(16-20) 607. m ftTITLD(21-25) 51,2.m.
4
... TITLD(26-45)
NMP JointFrequency Distribution Report (JFD) 5,
TITLD(46-65)
Nine Mile Point Unit 1 Main Stack to:EAB/LPZ 6
NVEL.
12 categories SNDIS....
2 distances, 7
';A-0 m. (no input needed for stack releases)
D, 0 m(no input needed for stack releases),
HS 106.7-m STOWERH 60.7 m 8
CALM(J)
- 0 (for all since KOPT(8)=0) 9 FREQ(K,;IJ)
See Table 5.1-2 10 UCOR A1 UMAX(I)
- 1=1: 0.44 mrs, 1=7: 6.0 mros 1=2:1.0m/s" 1=8: 8,0rmos 1=3: 2.0 m/s 1=79: 10.0 m/s 1=4: 3.0 rn/*/s I1-0: 13.0 mIs 1=5: 4.0,m/s 1=1: 118.0 m/s i=6: 5.0.mrns 1=12; 60.5 rmis 11 BDY(K,I)
K 1=1 n)..
S 2,000:
6,116 SSW 1,500 6,116 SW 1,200 6,116 WSW 830 6,116 W.
830 6,116
- WNW, 830 6,116.
NW' 830 6.116 NNW' 830 6,116 NN 830 6,116 NNE' 830
- 6,116 NE' 830 6,116 ENE'
- 830 6,116 E
1,900 6,116 ESE 1,900 6,116
_SE 2,300 6,116 Page 8 of 45
n-A2A?
-r j4,d ev
- Constellation Nuclear Se&vices l4.
Calculation No:;. NMPAST-01-001.
Rev. 2 Date: Dec. 19, 2003
'Card Variable..
Data Input Type Name SSE "2,000 6,116 12.
TAF(K,I)
K
.1=
I=2
- 1.-0 1.0 13
'DIST(K;I)
K
=1 t=2 All 3000: i 6000 mn 14 HT(K;i)
'K 1=1 (M) 1=2 (m),
-19
'39
.... ~ ~~~
W.
.4 3....
WSW 0ý.
0 W-0 0
WNW 0
0 NW 0"
0 NNW 0
0 N
0ý 0.
NNE 0
"0:
NE 1
31 ENE 3
"6 E
14 28 ESE 16..
Represents a coastal sector. Theselecteddistanceýof:830 m represents the distance from the Unit 1 Main.
Stack to the EAB in the WSW sector. The.WSW sector cortains the minimum:distance*foi the Unhit
- 1 Main Stack to the EAB :for all land sectors;.
Table 51-1.b PAVAN Input forUniti ReactorBuilding Blowout Panel Release Card
- Variable, DataInput Type Name.
1 KOPT(114, 0
6,.8-9 KOPT(7;.10) 1 2
TITLD(1-5)
Nine Mile Pointý
. TITLD(6-1:0) 1/01/976to 12/31/01 TITLD(!1 -
Ground Level Release 15)
.3 TITLD(167 60.7 m.
20)
TITLD(21.-
51.2 m 25) 4 TITLD(26-INMP Joint Frequency. Distribution Report (JFD).:
45)
.5 TITLD(46-Nine MilePoint Unit 1 Reactor Building Blowout Panel to EAB/LPZ
!65) 6
.NVEL 12categories.
ýNDIS:
0 distances 71 A
2082 m2 (per Reference 19 and:20),.
-D 42.2 m Page 9 of 45
ConStellation Nuclea SRces; Calculation.No: NMPAST-O1-001 Rev. 2 Date: Dec. 19,;2003 Card Variable.
Data Input Type6 Name HS:.
lOre TOWERH 60.7Tm 8
CALM(J)
.0 (for all sinceiKOPT(8)=0) 9:
' FREQ(KJ,IJ)'.See Table 5.1-2
- S e T a l 5.1 -2 10 UCOR UMAX(I) 1=1: :0444 m/s 1=7:6 0m/s *
!=2: 1.0 m/s.
1=8: 8.0 m/s 1;-3: 2.0. m/s 1=9: 10.0,m/s.
1=4: 3.0 m/s
'1=10: 13;0 m/s 1=5: 4.0.m/s
ý1=1 1: 18.0 m/s 1=6: 5.0 m/s 1=12: 60.5 mts
- 1.
BDY(K,I)
I1 (meters):
1=2 (meters)
S 2,000 6,116
.1200 6,116 WSW 830 6,116; W1 830 6,116 WNW.
830 6,116 NW1 '830 6116 NNW1 830 6,116 N.
830 6,1116 NNE.
830 6,116:
E 830.
6,116 ENE.
830.
6,116 E
1,900 6,116 ESE 1,900 6,116 SE 2,300 61,116 SSE
- 2,000
.6,116
- 12.
TAF(K;l!)
No input required (KOPT(9)=0)
- 13.
DIST(KAt)
No input required (ground. level release) 14 HT(K,l)
No input required (ground level release)
- !Represents a coastal sector. The.selected distance of 830 m represents the.distancefrom theUnit 1 Reactor Building Blowout Panel tothe EAB-in the WSW sector. TheWSW:sector contains the minimUmn distance fromr the Unit 1 Reactor; Building Blowout Panel to:the EAB for all land sectors.
Table 5.1-1.c PAVAN Mnputfor Unit 2 Main Stack Release
[Card Variable Name Data Input 1
.KOPT(.I4, 6,8) 0 KOPT(7,9-10) 1 2
TITLD(1-5.)
Nine Mile Point TITLD(6-10) 1/01f97 to 12/31I/01 TITLD( 1.1-15)
Elevated 130.8.meters.
3 TITLD(16&20)
.60.7.mi
_ TITLD(21725) 51.2 m 4
TITLD(26-45)
NMP Joint Frequency Distribution Report (JFD)
,5 TITLD(46-65)
Nine Mile Point Unit 2 Main:Stack;to EAB/LPZ
.6 1 NVEL 12 categories Page 10 of 45
Constellation Nuclear Services
~k7~- 4~
Calculation No:'NMPAST-01)O01 Rev. :2 Date:.Dec. 19,. 2003 Card: Variable Name
'Data Input Type NDIS 2.distances' 7.
A 0 0mz(no input needed 'for stack releases)
-D 0 m (no input needed for stackTreleases)
HS..
130.8m6 TOWERH 60.7 m 8"
CALM(J)
>O (for all since KOPT(8)=0) 9 FREQ(KI,J)
.See Table.5.5.1-2 10 UCOR
-1 UMAX(!)
W.1=!:044 m/s l=7:,6.0 m/s 1=2: 1.0 m/s 1=8:"8:o&rn/s
'1=3:'2,0 m/s 1=9: 10.0 m/s 1=4: 3.0 m/s 1=10:13.0 mt/s 1==5: 4. mIs
'H:A 18.0 m/s 1=6:.5:0 mr s
!1=12: 60.5m/s.......
1`1 BD=(K,l) "1K 1(n).
1=2(m)
S
.2256 6:116 SSW 1,936 6,11T6 SW 1,615 6,116 WSW 1,615 6.11,6
- W.
1,555 6,116 WNW' 1,555 6,116' ANW.
1,555 6,116
- NNW.
1555 6,116 i
- IN 4 ;5 5........
i............
6.1.
NE 1,555.
6,116
- NNE' 1,555 6.1 1B NE' 1,555 6,116
,ENE" 1,555 6,11:6 E
1,555 6,116 ESE 1,555 6,116 SE 1,600 6.116
-SSE 2,:134 6, 116
.12 TAF(KI)
K 1=1 1=2 Al 1.0 1.0 13 DIST(KI)
XK 1=
1=2 All 3000.m 6000 m 14 HT(K,I)
K 1=1 (in) 1=2:(mn)
',S 28 57 SSW
'19 39 SW 19 39.
WSW
- 0:
0.
W 0
.0
-WNW 0
0
.NW 0
0 NNW
'0 0
N 0
0
- NNE 0
0 NE 1
3 ENE 3
6 E
14 28 I ESE 16 32 Page 11 of 45'
aConstelation Nclear Services, Nz-i C~74-cN Caiculation No: NMPAST-01-)0,11 Rev. 2 Date: Dec. 19, 2003 Card Variable Name,.
DatalInput Type,-
SE 11 22
__"_SSE, 14 27 1 Represents a*coastal sector. The:selected distance:of :1,555 m :representsfthe distance'from the.Unfit,2 Main Stack to the EAB*i6the E and;ESE sectors. TheE and ESE sectors contain. the minimumrdistance from,the-Unit 2'Main Stack to the EAB for all land sectors.
Table 5.1;.d PAVAN InputforhUnit 2 Combined Radwaste and Reactor Building Vent Release
-Card Variable Name Dataln put Type 1
KOPT(!-4,6, 8-
-0 9)
KOPT(T,10)
I
- 2 TITLD(1-5)
Nine Mile Point.
- TITLD(6-40) 1/01t97.to 12/31101 TITLD(11-i15)
Ground Level Release 3
TITLD(16-20) 60.7 m TITLD(21-25) 51.2m 4
TITLD(26-45)
NMP Joint Frequency Distribution Report-,(JFD) 5
.TITLD(46-65)
.Nine Mile Point Unit:2 Combined Radwase/Reactor Building Vent to:EABILPZ 6
NVEL 12.categories NDIS.0 distances
.7 A
2844 m4 D
.51.9m.
HS lO: M TOWERH 60.7nm "8
CALM(J) 0 (for all :since.KOPT(8)=0) 9 FREQ(KI,J)
See Table 5-2
.10 UOR.
.1 UMAX(!)
1=1.: 0.4 m/s.
1=7: 6 0.ml/s 1=2:.1.0 mIs 1=8: 8.0 'ts 1=3. 2.0
- rn/s
=9:10. rn s J=4: 3.0 mis 1=10: 13.0 rn/s 1=5: 4.'0 rn/s I= 1: 18M0.m/s 1=6: 5.0 m/s...
12:60.5 m/s 1-BDY(K,I)
K..
1=1 (meters) l=2:(meters)
S 1 945 6,116 SSW 1,695 6;116 SW.
1,381-6,116 WSW 1,381 6"116 W7_.
1,381 6,A116 WNW' 1,;381 6,116....
NW1 1,381 6,116 NNW' 1,381 6,116
- N 1,381 6A116
- NNE' 1,381 6,116
ýNE' 1,381 6,116
_ENE' 1,381 6,116 Page 12 of 45
o nse llation 4
Nulear :Services CalDculation No: NMDpAST 1-902 Rev. 2 Date;: Dec. 19, 2003:
Card Variable Name, DatalInput Type E
1;686 el, 16 ESE....-
1,686 6,116
-SE 1,743 6,116 SSE 2,094 6,116 12 "TAF(KI)
No input required (KOPT(9)=0)
.13
. DIST(Kj)
No input.required (*round level release) 14 HT(K,!)
Noinput required (ground level release) 1: Represents a coastalfsector. The selected distance of.:l,381 m rrepresents the distance from the Unit 2 CombinedRadwastelReactor Building Ventitothe EAB in the.SWVand WSW sectors. The SW and WSW
.sectors contain the; minimum distance;from the.Unit 2 Combined.Radwaste/Reactor Building Ventlto the
.EAB for all land sectors-Table5A1-2'Card9:Inut 2:K=.1 3
234 5 6
- 7 8
9 10 1-1 1213.i1*4. 15: 16
.=1 0
0 0
O0 0 0
.0
- 0 0
0 0
0 0
'0 0
1=2,0 0
0
'0 0
'0 0 0 60 0 0 :1 0 1 :0 1=3 7
1 2 0
0 2
01 0 3.
2 0 4 7 10 25 1=4 44 18 3
1 1
1 1 :3 3
0 1
1 7 33 63 64 1=5 45.42 14 0
2 6
4 3
0 0 10:9.34 64 65
-1 643 40 50O 0 8 16 127 38 1 46 1'8 29 553 1=7 45 28 3
0
,0. 51711 8
2 1 91 25. 19 37 44 1=8108 70 5
1 1 5.24126 3 4
0172 35 36 71 87 1=9 85 45 2
0 :0 1 19 101 3
0 0 71: 211 29' :73 80 1=10 91 48 2
0 0 1
9 5
-0 0 0: 19 46 :691147121 1=1 124 21 0 0 0 60
.3 1
0 0
0 36 44141 95 31 1-121 71 0
0 0 0
.0
- 0 0
0 01 3;1634 :
0 i1
- 00 0
0 0.'0 0,
0 000 0 :1 %01 0
0
- 00 1=2.. "0 0 0O. 1.00
- .0 0 00 b
0
.:00 0 1=436 4:011 1 0 1
2 3
1 0_3 1 5
6 1-4 1A 15
- 11.
1 1
- 2 5
4 15 1
4 5 21 11 5
1-517 19% 7 3 06 8 17 13 4
0 9 23 24 6
9 i2' i=6 14 16 101 0
1 6 12 55 16:512 227 30 26 1412 J=7 17 11 1
01 1
7 21 18 10 3
0 36 25 11 27 20 1"8:56 37 6
1
.0 3 211 19 10 0
4 58 44*36 8250 1=9:57 45 010 0
8 6 9 01 138 58,36,65. 71 1=10 39.35 00 0
- 0
.2 1
- 1.0. 0.33 62 84 95151 i=1 115 *1.3
'0 0 1(0 0 0
0 0 0
0 39 83 83 ý301 9
1=12 00 ý 0
0 0
0 0
00 0
0 5 16 5
00 0
J=3
=1ýj01 0 (} 0
'0
.6' 0 40 0
0 0
0 0 :
0- 0 (0
1=2 1,0 0
0 0 i0 1010 0
.0 0 3 10 1=3 10 2
1 2
ý3 2
1 2
0 3_3__3 4 11 6
1-4 10 22 20 2
3 4
8 4
4 8
2 5 20 17 22 13 Page 13 of 45
ZJC*Tý.
c onstellation SNuclear Services Calculation No:,NMPAST-01 -001 Rev. 2 Date: Dec. 19, 2003 K1 11 2 3
4 5: 6 7 18 9,:10-11 12 131 14'15 16.
- 1=5 1:8 22 :15__7 0 :19 17 27 122 7
- 3 16 42 26 1il 9 1=6 11 25 7
0
- 0. 6 16 25 32 8
025 47 321 14 15
=72.17.4
'0 1
73 2736 6
336321 43 27
- 1=8 84 71 1:2
'01 1
7 29 27.21 2
3 69 586 58 84 45 1=9 54 53
- 6. 0. 0 1 21 9 17 3
0 26 80 73 85 57 1=10 38 57
'6 13 0 0o 20 t5 2
0 ý5 591130 84 62 55 1=11 20 18
ý0 0
0
(
1.0 0
0 1 62-:98:95.19 1
o 112 0
1 '00 0
0 0
0 9 12 5
1 !0
'1=1 0
1 0.:0 1
1. 1 1
1
.1 12 0
1 -0 2 0
1=2 4
7 9 8 4
4 5
2 6
4 3
6 7
.2 6
5 11.3",36 49.,61 44.45 33 25 35 15.24 23 18 33 :51 50140 S
84 101129 73 51 83 81 63 61.62 38 611.17 82 73 60
.l=i 651051:81 67 66 97134129132108 58 99178 94 70 50 1=6 94108189 37 51100 18511431199 172 92160181104 81 8-7 1=71041134137 18 45153289117: 2.1619811441219178131127106 1=81701356185 12 291795871332 i22761229144,3394300 231188 1=9 100 234 79:
1 3 79303191:179 40 140 298 3761232120411i9 1=10 98161 '29.0
'1 14125 67 45 -10 49 286 3871251117 62 1=11 33,40 1
.0
.0 2
111 0,3 0 2195289139 23 14 1=12 0
0:0.
0 0 (
0 0
00 02 0 201:241 2
0 01=10 0
.0 1
21 2
'011 100 0
2 1'
=2, 8
7
- 6 8 17 8 5 2 :5 5
6
- 8 3
311 5
- 1=3 27 23 52 34 32 25 16 27 16 20 31 45 :29 31 13 20 1=4 35 42 73 92 57 491 33 46141, 37 51 58 95 56 41 39
- 1=5 27 31 '93.7.1 71,:63 74 83 52 48 60102 98 38 29 15 16 2,1 33 ' 28 38 73116104106 108 97212102 37 12 18 17 16=23 24, 10 16 762461702131216,13911.83 84 22 12 20 1=8 36 29.17.4 I5 67 630605 614 404 2133491;36 ":52 30 19 1=9 24 18.4. 6 0. -0 11 235320245 58 62236105 54 21 11 1=1 0 18 23 5
'ý0 1 2 44 62 24 1
7175106,54
- 7 12 1=11 2
6 0 0
01 5
1 0 0 2 56 5620 5: 1 1=121 0
0 00 0
0
_5 4
2 :0
'0 J=6 1=1 10 01C
- 0 i.I
,0 0 2
1 01 1 _
2 0
1=2 "4
9 263 0
14 2
9 4
22 1
5
- 1=3 13 15 22 26 21 12 -161 13 14 14:25 28 21 24 25 12 I1 17 19 40 41 30 32 21 18 17 i17 30 40 44 34 10 15 A"5
- 8 13 17 23 51 21 26 27 18 23 '58 80 38 21 12 9
1=6 9 10 6 16 22 25 36 39 33 31 70 171 39 9 8 11 1=7 9
11 4
2 18 45 39 '52 30 42 85 53 18 3
2 7
P:8. 13 7
5 0
8 24109187158138 93 50 24 15
,3 f6 1=9 8
7 2
0 0
0 8 25 25 17 1 20 26 9
8 9
=1010.0 0
0 0 1
0 0 o :0:17 28 7
512
'Page 14 of 45
~4Zic7~~4' Const elation Nuclear Services
ýCalculation No.: NMPAST-41-001 Rev. 2 Date: Dec. 19,12003 K
1: 2
.3 4
5 65:7 8
9 10 11 12 13 14115:16 1=11 o0 0
0 0o 0.0 0
0 0 0 011 5
1 0
0 1=12 0
0 0_0 0o 0 0 0 0
0 0
0 0
0 0
0 41 1
1 0 0 3
1 0
4 1
1 1 0 1
1 0
1 1=12 7
7 8 10 12 6
8 8 14 5
5
- 7 14 11 7
4 1=3 211 25 27 33 32 ý36 23 25 31 28 46 44 33 34 13 26 1=4 14 15 36 30 49 38.25 27 31.42 58 62"40 21 12 12 1=5
- 8 101 3 16 37 30120 41 26 46 ý86 81 17 7
3.. 5 16=
5 20 _
'3 21 33135 34 40 52 80 54 121 0
1 3
1=7 1
4 2_2 7 2829054145147 63 18 5
1 1i 2 I =8.10 10 1
0 4 19 36 95' 90 45 21 14 4 1 :3 7
1=9 14 5
10 0
0 322 0 0 3
7 1 4
8
=10 89 0
0
- 0 0
0 0 0
0 0(
87 8
1 3
6 I =1
,21 01 0 0.
0 0 0
0 0
0 '2 1 1 1
- 0 1=1 2
01 0 0 '0 01 0
1 0 00
.0 0
0
- 0 I Wind Speed Category, J = Stability Category,:K =wind Direction Table:5.2-1 Input References for Similar PAVAN 'Input Files PAVAN Input File.
.Similar PAVAN In putFile
.Unit 1 Turbine Building Blowout Panel Unit 1 Reactor Building Blowout Panel!.
Unit;2 Main Steam Tunnel I Unit 2 Com bined: Radwaste and Reactor BuiIding Vent' Unit 2 Standby Gads Treatment System Building Unit 2 Combined Radwaste and Reactor Building Vent Unit 2 Sampling systern Panel
'i Unt2 Combined Radwaste and Reactor Buildin6 Vent'I
- 6i Calculation and Results 6,1. DeterrninationIof Distances for Calculations,
.Forstack releases, the maximum ground-level X/Q. in a sector may occu r at a distance beyond the EAB and LPZ. R;G. i.;145 (Reference 2), recommends making X)Q calculations for each sector at each: minimum boundary distance and at various distances:beyond the EAB to determine where the maximum concentrations occur. Test cases in PAVAN were performed
.at both Units for the following distances (in meters):
1W0 535 1750
- 1750 4500 7000 250 550 850 2000 5000 8000
.500
- 600 1000 2500 5500 9000 510 650 1250 3000 6000
!525 700 1500 3500 6500 Figures 6.1-1 and 6.1-2 show the results of the test cases. For both Units, it was determined.
,that the maximum X/Q values occur at the EAB and LPZboundaries. All input files, output Page 15 of 45
ont atnCalculation No:,NMPAST.01-001,
- Rev. ý2 3Nulear Services "ate:.
Dec. 1% 2003, files andother files related to theltest cases are included in the Maximum Stack XQ Distances folder on the enclosed CD.
6.2. ENVLOP Programming:Error:
As. mentioned in the CNS.PAVAN Computer Code Verification (Reference 15), the PAVAN ENVLOP subroutine has, a programming error*or "bug." As a result.. 0.05% X/Qs for non-coastal sectors were visually checked, in each. PAVAN output.*file. Twenty-eight: cases were hand-checked where th e.0.5% )JQ was not, bounded, or near neigh"boring, points. These cases included:
Unit 1 Main Stack to EAB -SSW Sector Unit, 1 Main Stack to EAB -. E Sector
- Unit-1 MainStack to EAB -. ESE Sector o Unit 1 Main Stack to EAB - SE Sector.
- Unit 1 Main Stack to LPZ - WSW Sector
- Unit I Reactor Building Blowout Panel to EAB,- SWI Sector Unit 1 Reactor Building Blowout Panel :to EAB-. WSW Sector
, Unit I Reactor Building Blowout Panel to EAB
- E Sector
- Unit I Reactor Building Blowout Panel to LPZ -SSW Sector
- Unit I Reactor Building Blowout Panel toILPZ - SW Sector Unit ' Reactor Building Blowout Panel to LPZ - SE Sector
' Unit 1 Reactor Building Blowout Panel to LPZ - SSE Sector
- Unit 2 Main Stack to LPZ - S Sector W
Unit 2 Main Stack to LPZ:.- SW Sector o Unit 2. Main Stack to LPZ:-WSW Sector
, Unit 2Main Stack to LPZ.- ESE Sector
- Unit 2 Combined Radwaste/Reactor Building Vent to EAB - SW Sector 4 Unit 2 Combined Radwaste/Reactor Building Ventlto EAB - WSW Sector Unit 2 Combined Radwaste/Reactor Building Vent to. EAB - SSE Sector
, Unit 2 Combined Radwaste/Reactor Building Ventto LPZ-SSW.Sector Unit 2 Combined Radwaste/Reactor Building Vent to LPZ-1SW Sector 4 Unit. 2 Combined Radwaste/Reactor Building Vent to LPZ-. SE Sector SUnit2:Combined Radwaste/Reactor Building Vent to LPZ -SSE Sector As a result, the.X/Q Values which were equaled or exceeded 0.5% of the time for these runs and ;sectors were manually verified.:in Microsoft@ Excel@, based on the upper envelope of the ordered.X/Q frequency'values extracted from the PAVAN output files. These values represent Page 16.of.4 5
Calculation No: NMPAST-01-001 dRev.
2 Nuclear Services Date: Dec. 19,2003 the.*0 -2hour X/Qs for the-sector. It was determined that all 1the 0.5% X/Q values were calculated correctly: by PAVAN, and are therefore valid. Hence, the PAVAN outputvalues were extracted and required no.additional processing. These calculations are included in'the 0.5%,Sector Dependent Calculations folder on the attached disc.
6.3. ENVLOP Error According to the PAVAN user's guide (Reference8), an error occurs in the ENVLOP subroutine when the total number of values in the arrays X and Y used in obtaining upper-enveloping lines exceeds 98. This number overflows arrays.X and Y. As a result of:this error, the overall site XQ value which is equaled or exceeded 5.0% of the time was notobtained.in six of the PAVAN calculation runs. The six-runsincluded:
v Unit:1 'Main Stacklto.EAB Unit I Main Stackto LPZ Unit 1 Reactor Building Blowout Panel to EAB Unit 2 Main Stack to'EAB
- Unit 2 Main Stack to LPZ
- Unit 2 Combined Radwaste and Reactor Building Vent to EAB As a result, the overall site X/Q values which were equaled or exceeded..5.0% of the :time for these.runs were manually calculated in Microsoft Excel, based on the upper envelope of,
,the orderedX/Q'frequency values extracted from the PAVAN output files. These values represent.the
- 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> overall site X/Qs. In addition, the:intermediate time-period overall site X/Qswere manually calculated using the PAVAN algorithm coded into Excel spreadsheet
- fornm. Intermediate time points of 8, 16, 72 and 624 Were utilized.in this spreadsheet algorithm, which is replicated from the PAVAN algorithm. These manual calculations were performed.
using the methodology as described in R.G. 1.145.(Reference 2). a!nd the PAVAN user's guide (Reference 8)., These calculations are included in the 5%,Site Limit Calculations folder on the enclosed CD.
6.4. Results 1Results of PAVAN: calculations are incuded in Tables 6.4-1 through 6.4-5.. The actual :PAVAN outputfiles are included in the Output Files folder on thegenclosed CD. Table 6.4-1 lists the 0.5%-sectordependent 0 -2 hour (non-fumigation) X/Qs along with the fumigation X/Qs calculated with PAVAN for stack releases.for non-coastal sectors. Tables 6.4-2 through 6.4-5 lists both the sector dependent and overall site'limit X/Qs for non-coastal sectors,.,
Page 17 of445
Constellation Nuclear Services CalculationNo: NMPAST-01-001 Rev. 2 Date: bDec:`19, 2003-Figure 6.1-'1LUnit I Main Stack X/Q Versus Distance 5 oE706:-"
5.00E-06 4.50E-06 4.00Et06,
- Z3.50E-066 3 OOE-
- 06 1.150E-06 I.00E-06 5:OOE-07 distance (m)
Page 18 of 45
Constellati o Nuclear.Services.
Calculation,No; NMPAST.-01-*O1 Rev. 2 Date:-Dec. 1.9,2003 Figure 6.1-2 Unit 2 'Main Stack XIQ Versus Distance*
3..50E-06ý 3OOE-fl6 i.5OE.O6 S2.OOE-06.
1.50E-016 1.00E-06 5.00E607 distance (m)
Table 6.4-1 Nine: Mile PointO:.5% Sector: Dependent Short-Term XIQs Calculated with
ýPAVAN.....
Source Sector Non-Fumigation Fumigation EAB.
Non-Fumigation Fumigation.LPZ" 0-24Hour ýEAB XIQ X/Q (seclm 3) 0-2 Hour LPZ X/Q
-xjQ.:(secdlm3)
(seclm)3 (secim 3)
Unit I S
3.78E-06 3.28E-05.
2.87E06 2.12E-05
.Main SSW 2.98E-06V 3.85E-05 1.22E-06 1.55E-05 Stack SW 3.46E-06..
462E-05 12.66E*061 1.55E-05 WSW 1.55E-06 5.98E&05 1.. 25E-06" 9.85E406 E
2.57E-06 '
3.09E-05
- 205E-06 1.34E-05 ESE 2.60E-06-'
3.13E-05 2.06E-06T 1.41 E-,05 SE 2.21 E-061 2.59E-05 1.67E-06:
1.24E-05.
SSE 2.18E-06 2:96E-05 1i6 E-06 1.32E105 Unit 2 S
- 2,19E-06 2:36E-05 1.73E*.6 1 1.42E-05 Main SSW 1.79E-06 2.51E-051' 1.49E-06 1.15E-05 Stack SW 1,97E-06 2.90E-05 1".75E-06' 1.15E-05 WSW 8&82E-07 2,,68E-05 7.80E-071 8.04E-06 E
1.64 E-06 2.93E-05 1.43E-06 1.02E-05 ESE 1.69 E&06 296E-05 1.28E-06' 1, 06E-05 SE.
1.44E-06 2.83E-05 1.06E-06' 9.66E-06 SSE 1.31 E-06 2.25E&-05 1.04E-06' 1.01E-05 1
Value manually verified in accordance with;Section 6.2.
Page 19 of,45
c~r(0-4 ij~
Nuclear Services
,Calculation No:.;NMPASTO 1-01 Revi 2 CDate:;Dec. 19, 2003 ThbIt~ Rst-2 Unit I M2in Stank Nnn-Fumin~tian XIQ Valii~
X/Q:(se Jm,"
Distance Sector 0-2 0,8 8-24 1-4 4-30 Annual
______Hours.
- Hours, Hours Days Days Average S
3.78E&06 1.68E-06 1,12E 4-65E07" 1.31E-07 2.80E-08 SSW' 2.98E-06 1.36E 9.21 &E07 3.94E-07 1.16E-07 2.62E&08 SW 3.46E-06 1.35E-06
-8.40E07 3.02E-07 6.93E-08 1T.15E-08 WSW.
1.55&-06 4.75E-07" 2.63E-07: 7.30E-08.:I6E0 1.22E-09 EAB
'El___.....
2.57E-06 1.29E-06.T 9:110E-07, 4.30E-071 1.46E-07 392E-08 ESE.......t 2.60E-06 1.24Er-06: 8.62E;07 3.88E-07 1.23E-07 3.03E-08 SE 2.21,E-06 1.06E-06 1 7.36 E-07.
332E-07' 1.106E-07
`2.61 E-08
ýSSE 2.18&E06 1.01 E-06 6.89E'-07 2.99E707 9.02E-08 2.08E-08 Overall'Site' 2.61 E-06 1.30E-06 9.22 E-07 4.34E-07:
1.47E-'07
" 3.92E-08 S
2.87E-06 1.26E-06:1 8.40E-07 3.45E607 9.62Ew08
?2!02E-08 SSW 2.22E-06 1.03E-06' 6.96E-07' 3.01 E-07 9.01 E-08 2M.6E008 SW' 2.66E-06 1.21&E06 8.13E&07 3A5E&07 1.01 E-07 2.24E -08 WSW' 1.25E-06 5.22E-07 3.38E;07 1.31 E-07 3.37E-08 6E41E-09 ILPZ E.
2,05E-06 1.01:E-Ub:
7.12E-07
'3.32E-07 1.11E-07' 2.89E-08 ESE' 2.06E-06 9.59E-07:: 6-54E-07: 2.85E-07 8.-66E-08, 2.01 E:08 SE 1.67E-06 7.68E7071 520E-07 2.23E&07 6.63E-08 1.50E-08 SSE 1.61 E-06 7.25E-07 '4.86E-07' 2.04E-07 5.88E-08 1.28E&08 Overall Site I 1.90E-06 9.53E-07 6.74E-07 3.18E&07 1.8E-0788 : 2.89E-08 I1 With the exceptioh of Annual Average, all values: were verified in accordance with Section 6.2.
2 With the exception of Annual.Average, all values were calculated In accordance with Section 6.3._
Table 6.4-3 Unit I ReactorBuilding Blowout Panel X/Q Values:
X/QO(s c/mrn Distance SeCtor-0-2 0-8 8-24 14, 4-30 Annual Hours Hours
- Hours Days Days Average.
S 4.59E-05
- 2-48E-05 1.83E-05 9,39E-06 3.61 E-06 1.12E&06.
SSW 6.34E:05 3.72E-05 2;84E-05 I*.59E&05'
ý6.93E&06 2.50E-06 SW'
.102E,04 6.2!E-05, 4.84E-05 2,81E-05 f.29E-05 4.99E-06
- WSW, 1.58E-04 9.48E-05 7.35E-05 4.24E&05 1..92E-05 T729E&06 EAB
- 2.32E-05 1.25E-05:
.162E-05 1,20E-05 6.21E-06 2.412-_06 T760E-07 SSE 4.11E-05 2.23E-05.
1,64E&05 8.43E-06 3.24E-06 1.:01 E-06 Overall Sitez 1.90E&04 1l.28E-04 1".05E-ý04 6.80E-05 3;67E-05, 1.72E-05 LPZ.
S 1.3.1E-05 5:96E-06 4.03E-06 1.72E-06 5.05E-07 1.132-07 ISSW' 1.33E-:05 6.17E-06 4.20E-06 1.82E-'06 5.51E-07 1.27E-07 SW" 1V81E-05 8.19E-06 5.52E-06:
2.34E-06 6.82E-07 1.51E-07 Page 20 of 45
IAZA ckr"T"(:ýv-SConsteLation Nclear Services,
- Calculation No: NMPAST-O1-001 Rev. 2 Date:: Dec. 1, 92003
-X/Q (sec/e)
.Distance Sector 0-2 08, 8-24 14 4-30 Annual Hours
- Hours, Hours Dlays Days!
Average WSW...
2.07E-05
`8.99E-06 5.93E..06
- 2.40E-06
- 6.57E-07 1.34E-07 E
2,31 E-05 I;08Ew05 7.35E-06 3.21E-06 9,80E-07 2.29E-07 ESE
.1759E-05
.40E-06 5.'05E-06
.2.20E-06 16.68E,07 1.55E&07 SE' 9.24E-06 4.38E-06 3.01 E-06 1.34E-06 4.19E;07 1.01 E-07 "SSE' 1.I.OE-05.
'5-09E,06 3:45E-06 1.49E-06.
,4.46E-07 1.02E-07 Overall Site 3:58E-05 I,.63E-05 1.I0E-05 4-67E-06.
1.37E-06,
.3,04E-07 1
With, the exception of Annual Average, all values were verified in accordance with Section6.2.
2 With 4the exception of Annual Average, all values were calculated:in accordancewith Section 6.3.
....Table 6$.4-4 URit 2 Main Stack Non-Fumigation XQ Values
.. Xj/Q(S ec/m_)*
DiStance Sector G0-2 0-8 8-24 1-4:
4-30
- Annual, Hours Hours _
Hours Days Days Average
.S 2.19E-06 9.70E707 i6.45&E07 2.67&E07 7T49E-08
.b596-08
- .SSW 1.:79E-06
.8.1 E-07 5.46E;07' '2.31 E-07 6.75E-08 1.50E-08 SW
- 1.97E-06.
7.71 E-07
- 4.83E&07 1,.75E-07 4.06E-08, 6.80E-09 WSW 8.82E-07
- 3.01 E-07 1.76E-07 5_50E&08 ý 1,03E-08 1.33E-09 EAB E
-1.64E-06 7.81 E-07 5,40E-07
'42A2E-07.
7.64E'08:1 1.687E-08
.ESE i1 69E-06.
7-84E-07 5.34E-07 2.32E-07.
7.02E-08 1 :63E-08 SE 1.44E-06
.6.86E-07 4.73E-07 2.211E07 6.65E-08 1.62E-08 SSE ji.31E-06 6.05E-07 4.iE-07 1.77E,07 5.29E-08.1.21E-08 Overall Site2
- 1.56E06 7-53EM-07 5.22E-'07
- : 2-36E-07" 7154E'08 1.87E-08 S1 IS.73E-06 7.,79E-07 5.22E-07 220.E07
ý6.33E-08:
1.38E-08 SSW 1.49E-06.
6.94E-07 4.75E&07 208E-07
1.75E-06
8.0 1E-07'
5.41 E-07 2.31 E-07 16.82E-08 1.53E-08
- WSW, 7.80E-07 3.25E-07.,2.09E-07 8.09E&08 2.06E-08 3.88E-09 LPZ E
1.43E-06 7.05E-07 4.95E-07.
2.30E 07 7.65E-08 1l.99E&08 ESE' 1.28E,06 6.08E-07 1:87E-07 5.85E-08:'
1-41 E"08 SE' 1.06E&06 4;98E-07 3.41,E-07 1_.50E&07
-4.62E-08 1 09E-08 SSE' 1.04E-06 4.76E-071 3.22E-07 1.37E107 4.046E-08.
9.13E-09
- Overall Site I.2UE-06 6.1-:0E-07] 4.34E-07 2.08E-07 7.24E-08 1.99E-08 1
With the exception of Annual Average, all values were verified in :accordance with Section 6.2.
2 Withthe exception of Annual Average, all values were calculated in accordance with Section
'6:3.
Page.21 of 45
aConstetlation Nuclear Services
~Ac.cVr~-c~4 Calculation WN: NMPAST-01-001 Revae2 Date: Dec.d.19,.2003, Table.64-5 Unit 2 Combined Radwaste/Reactor Buiiding Vent X/Q.Values`
X/Q (sec/m)
Distance Sector 0,2 0-8 8-24 1-4 4-30 1Annual Hours Hours Hours Das Da ys Average S.
4.65E-05
- 2.51 E-05 1.85E-05 9.46E06 3.62E-06 1.12E-06
-SSW
'5.47E-05 3.1 OE-05 2.34E&05 1.27E-05
- 5.25E-06:
1.79E-06 SWn',8.75E-05j
-5.12E-05 3.91 E-05 2.1i8E-05 9.46E&06
'3.40E-06 WSW1 9:14E-05 5.13E-05.,3.85E-!05,.206E-05 8.38E-06
- 2.79E-06 EAB.
E
.80OE-05 4.70OE-05.
3.60E,05 Z.,03E&05 8.855-06 3.22E-06 ESE 6.22E-05 3.57E-05, 2.70E-05 1.48E-05:
.23E-06 2.16E06 SE 4.07E-05 2.32E-05 ý 1.75E&05 95.4E-06, 1398E&06 1.36E-06 SSE" 3-85E-05 2.05E-05 1.50E-05:
7.,56E-06
.2.84E-06 8.54E-07 Overall Sitez 1
.i19E-04.
7.737E-05-,
5.80E-05 3A5E-05:
1.64E-05, 6:56E-06 S
4.15E706, 1.79E&06ý
,6.66E-07.
1.46E07 7
WSW 2'.07E-05 8-92E-06 5.86E-06' 2M36E-06 1.37E-07 1.29E-07 LPZ E
2.31 E-05 1.07E-05 7.28E-06' 3116E&06 9.56E&07-2.21E-07 "ESE
-158E-05 7.32E-06 : 4.98E-06: 21.16E-06,
&50E-07 1..50E-07 SE' 9.-24E-06
- 4.36E-06 2.99 E-:06I 1.32E-06 A.
411E07
.80E-08 S:SE*
1.OE-E05 5.06E-06; 3.42 Er06 1_.47E-06 I4.35E&07 9.83E&08 Overall Site I.58E-05 1.62E-05 1.09E-05] 4.59E-06 ]
1.33E&06 2.93E-.07 1I With the exception.ofAnnual Average, all Values were verified in accordance With Section 6.2.
- 2
- Withthe exception:of AnnualAverage,,al1 values'were calculated in accordaincewith Section 16.,3.
,7. Conclusions Tables 7-1 and 7-2 provide conservative atmospherio dispersion coefficients: (X/Qs)-to beused
,to perform calculations to assess radiation exposure at the EAB and LPZ due to postulated accidents occurring atNMP Unit 1 and Unit 2. Ground-level releases include releasesfrom
'the Unit 1 Reactor Building Blowout Panel,.Unit 1 Turbine Building Blowout Panel,'Unit 2
,Combined Radwaste/Reactor Building Vent, Unit 2Main Steam Tunnel, Unit 2 Standby Gas.
Treatment System Building and Unit 2 PostAccident Sampling System Panel. Elevated releasesdinclude releases from the Unit 1 Main Stack and Unit:2Main Stack.
Forthe EAB, 0 -2 hour XIQs selected for EAB evaluation -are assumed to last for the duration of the, accident.. X/Q values selected for evaluation at the :LPZ represent the maximum, of sector dependent and.overall site X/Qs for-each time interval. Fumigation,XQS are considered for elevated releases only and are conservatively assumed4to existfor 0,-8 hours at the LPZ.
All X/Qs selected for evaluation are consistent with !the. guidelines presented in R.G. 1.145 (Reference 2).
Page 22 of 45
CoNst elat io Nauclear Services C4 Calculation No: NM.PAST-01-001 Rev. 21 Date: Dec. 19, 2003 Table 7-1' Ground.-LevelRelease X/Qs Selected for Evaluation at NMP XIQ (telm Unit Boundary.
0-2 0-8 8-24 4-30, Hours Hours Hours
,Days EAB' I.'90E-043 1
LPZ:
1.63E,05 110&E-05 4.67E-06 1.37E-06
- EAB' 1.1 9&-D4333 2..
E 0 2
LPZ 162E-05 I 09E-05 4.59E-06 1.33E-06 1 D02 Hour)(X/Os at the EAB are conservatiVely assumed to exist for the duration of the iaccide t.
- 2,. X/Q Cvalues for eacih time interval at the:LPZ represent the maxim um of the sector dependenrt and overall site values.
3 Overall Site X/O Value.
Table.7-2 EleVated Release X/O Selected for Evaluation at"NMP Unit Boundary 0-2 0-8 8:-24 114 4-30.
Hours',
HOurs Hours i
.Days EAB7 5.8-0O5-'
.2.12E-05 8.40E-07 3
1.11E,07 EAB
.2.96E-057 2
LPZ.
1.42E-055 5.41E-07 2.31E-07 7.65E-08 1 0-2 Hour.X/Qs at the EAB are-conservatively assumed to exist for theduration of the accident.
2' X/Q values for each time interval at the LPZ, represent the maximum of the sector dependent and overall site values. Short-term fumigation X/Qs are conservatively assumedito exist.:for the first,8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s-of the accident.
3 WSW sector short-term fumigation-,value.
- 4. :ESE sector short-te6rm fumigation value.
5 S sectorshort,-term-fumigation value.
6: S sectorX/:
value.
7 SW sector X/Q value.
- 8.
Esector X/Q value...-
Page 23 of 45
Calculation.No: NMPAST-01-001 Conste.riauon Rev. 2 Nuclear Services_
Date: Dec. 19i2003
- 8.References
- 1. CNS Quality Assurance Program, Rev. 4, Decemberl, 2002..
2.. RegUlatory Guide 1.145, Rev. 1, TAtmospheric Dispersion -Models for Potential Accident Consequence Assessments at Nuclear Power'Plants", February 1983.
- 3. Regulatory Guide 1.111, Rev. 1, 'Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-*Water-Cooled Reactors",
July 1977.
- 4. NMPR.Purchase Order No. 02-40502, May 22, 2002.
- 5. Regulatory Guide 1.183, 'Alternative -Radiological Source Terms -for Evaluating Design Basis -Accidents at Nuclear6 Power Reactors", July,2000.
- 6. 10CFR Partlo0, :"'Reactor Site-Criteda", December 1996.
- 7. 10:CFR Part 50, "Domestic Licensing of Production and Utilization.Facilities", AUgust 1991.
- 8. NUREG/CR2858, "PAVAN
- An Atmospheric DiSpersion Program for EVaiUating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations",
November, 1982.
- 9. E-mail from Tom Galletta to Shane Gardner: and JamesHeffner (
Subject:
5 year:JFD's),
Attachment:
"NMP_60mJFD_1997-2001 for!CNS"', July 25, 2002.
-10. Meteorological Evaluation Services,. lnc. 'AccidentX/Q Values for Nine Mile Point Unit 1 Releases from the Main Stack and :,the Reactor and Turbine Buildings", August 7, 1990.
1.1..Meteorological Evaluation Services, Inc. "Technical Support Document Nine Mile Point Unit 2 Accident-and Long-Term Diffusion Estimates and the Methodology Used in their Calculation", December 1985.
- 2. NMP Drawing C-26658-C, Rev. 4, July 1974.
13.NMP Unit 2 USAR Figures 2.3-43 through 2*3-46, Amendment 3, June 1983.
1 5. CNS PAVAN ComputerCode Verification, Rev. 1, June 24, 2002.
- 16. NMP Drawing C-1 8713-C, Rev, 9, May 1974.
18.Teileonference-with NMP (Ted KUlczycky, AI Moisan,, Glen Stinson, Tara Neider-CNS, Shane Gardner-CNS, James Heffner-CNS),
Subject:
Exclusion of NMP coastal sectors from evaluation, August 8, 2002.
19.Teleconference with NMP (Ted Kulczycky, Al[Moisan, Glen Stinson, Tara Neider-CNS, Shane Gardner-CNS, David Matchick-cNS, Timothy Kurtz), September 10, 2003.
- 20. Memorandum CNS-03-218, "Comments on NISYS Review of CNS Calculations NMPAST-01-001 and NMPAST-02-001," Shane R. Gardner, September 24,2003.1 21.Regulatory Guide 1.23, "Onsite Meteorological :Programs," February, 1972.
Page 24 of 45
Conistellation Nuclear Services Calculation No: NMPAST-.1-001 Rev. 2 Date:: Dec. 19, 2003 Appendices Appendix A.- Figures:: EAB and LPZ Regions Showing Associated X/Q Directions Appendix B - PAVAN Output Appendix C - Listing of Fliles on DATA CD-ROM. for Calculation NMPAST-01 -001 Page 25 of 45
ic476-c~
Constellation Nuclear Services Calculation No: NMPAST-01-001 Rev..2 Date: 'Dec. 19, 2003 Appendix.A -,Figures: EAB and LPZ Regions Showing Associated X/Q Directions Page 126 of.45
Constellation Nuclear Service Calculation No; NMPAST-01-001 Rev. 2 Date: Dec. 19, 2003 Figure A-i EAB andAssociated X/Q Directions NNW, _iN NNE C
+
)~uA h a~U~I(I~1 Page 27 of 45
Wai c4~ -~L Co.stellation
- Nuclear Services Calculation 313 No: NMPAST-01-001 Rev. 2 Date: Dec. 19/,2O031 Figure A-2 LPZ andAssociated X/Q Directions NNW N
NNE NW NE
~. A ~
VYNW~
lquir WILE A01mr-I
-STACK O5Ow3KMR1.
MILE)
ENE
,-NINC MILE POIN~T-2 MT" 6XW I*ISLES) LOW POPULATION ZONEC I0JI(PARY SCALE - WIL 3
.4 0:
SCI LE-KILOMITdlims Page 28 :of 45
SConstellation Nuclear Services 14.
Calculation No: NMPAST-O1-O01 Rev. 2 Date: Dec. 19, 2003 Appendix B r PAVANOutput Page 29 of 45
SConstellation Nuclear Services 1USNRC COMPUTER CCDE-PAVANý VERSION 2.0 Calculation No: NMPAST-01,001 Rev. 2 Date: Dec. 19,2003 RUN DATE, 09-03-02 iPLANTý NAOE: NINE MILE POINT METSOROLoGIcAL INSTRUMENTATICN DATA PERIOD: 1/01/97 TO 12/31/01 WIN)
SE!SORS HEIGHT:
60.7 METER TYPE OF RELEASE-ELEVATED i06".7 METER
'DEALTA-T HEIGHTS: 51.2 METER.
SOURCE OF DATA:
JOINT FREQUE11CY DISTRIBUTION REPORT (JFD)
NINE. NILE POINT NUCLEAR STATI0N' COMMENTS:
NINE MILE POINT UNIT 1 MAIN STACK TO EAB/LPz PROC-RAN
- PAVAN, 10/76, 8/79 REVISION; IMPLEMENTATION OF REGULATORY GUIDE 1.145 0LA RIJ.TVE.CONCENTRATION (X/Q) VAkUE$ (SE(/C!J1,Cý METER)
VERSUS AVERAGING TIME HOURS PER YEAR MAX
-2 HR X/Q IS, EXCEEDED DOWNWIND DISTANCE SECTOR (METERS)
S 2000.
SSW 1500.
ssw isdo.
WSW
,830.
W
.830.
.WNW 83 0.
N*w 830.
NNW 830.
NE 8306.
N1304 830.
ENE 330-E 1900.
ESE 1900.
SE 2300.
SSE 2000.
MAX:X/O
-2 'HOURS 3 '78E-06 2.9,8E-06 3.4.6 k-066
- 1. 55E-06 I.43F-06 1,72E- 06 1.83E506 1.85E-06
- 1. 68E-06 1.36E-06ý 4.755-07 4.36E-07 6.46E-07 7;.72E-07 7.315 E- 07.
5.73E-07 4.56E-07 9.76F-07 I.29E-06 1.24E 06 I.06E-06
- 2. 625-07
- 6.795-07
. v105- 07 8.62E507 7.36E-07 6.89E-0; 1-4 DAYS 4.655-07 3.94E-0.7 3.02E-07 7,-30E-08 6.62
"-08 1.378-07 1.97E-07,
.9-7E-07 1,79E-07 1.17E-07 7.85E-08 3.09E-07
- 1. 165-07 6.93E-08
- 1. 1..-08 1.04E-08
- 2. 96EE08 S. 55E-08 5..09E-08 4.SIE-08
,2.
- 1. 39E-08
- 9. 990-08
- 1.
46E-07 1.23E507
.TOTAL HO
- 4. 615-09
- 9. 96E-09 9.7349-09 7349E-09 3.:605-09
- 1. 68E-09
'2.51E.-08 3.92E-08 3.03E508
'2 61E-08 2.08E-08 URS.AROUND SITE:.
I. SECTOR 41.7
ý22.3J 35.2 5.9 6.3 4..8 6,.
S..6 5.5 5.1 17'.5 1 6 ; 1 14,8 13.5 213.:7 DOWNWIND SECTOR SSW:
WSW W
WNW N
NNNE NE E
NEE SE SS3 8'
0-SRP.2 23..4 830.
4 -882E-OE 2.17E-06 41.46E-06 SITE LIMIT 0.0oE+.o0 0.00E+,00 0.00E+00 400.5 PERCENT X/01 AN INDIVIDUALIiS LIMITING.
OX/Q VALUES (SEC/CUBIC METER)
FOR FUMIGATION AT THE BOUNDARY.
DOWNWIkE DISTANCE FUVIGATION.
,SECTOR (METERS)
X/Q S
2000.
3.28E-05 SSW 1500.
13.85E-05 SW 1200.
4.62E-05 WSW 830.
5.98E'05 S
830..
5.98k-05 WNW 830o.
5.98E-05 NW 830.
E.9-05 NNW 830.
5.98E-0s N
830.
5.98E-05 TENS 80 5.98E-05
.NE 830.
C.O0E-05 ENE 830.
E.03E-05 1900.*
.o9-:05 ESE 1900.
3.135-05 3..92E-08 3..92E-08 0)J Page 30 of 45
OConstellation Nulear Services SE 2300.
2.'9i-60, SSEý 2000.
2.96E-0S Calculation No: NMPAST-01.-001 Rev. 2 Date: Dec. 19, 2003 At PD, Page. 31 of 45
'0Constellation Nuclear Services IUSNRC COMPUTER CODE-PAVAN, VERSION 2.0
/PLANT NAME:
NINE MILE POINT DATA PERIOD: 1/01/97 TO 12/31/01 TYPE OF RELEASE:
ELEVATED 106.7 METER SOURCE CF DATA:
JOINT FREQUENCY DISTRISITrION COMMENTSM NINE BMILE POINT UNIT 1 MAINMSTACK Calculation No:: NMPAST-01-001 Rev. 2 Date: Dec. 19, 2003 RUN DATE: 09-03-02 METEOROLOGICAL NlSTRUMENTATION WIND SE-4SORS HEIGHT:
60.7 METER DELTA-T HEIGHTS: S1.2 METER REPORT (JED)
NINE MILE POINT INUCLEAR STATION TO EAB/LPZ PROGRAM:
- PAVAN, 10/76, 8/79 REVISION, IMPLEMENTATICN OF REGULATORY GUIDE 1.145 0
RELATIVE CONCENTRATION (J/Q)
VALUES (SEC/CUSI? METER)
VERSUS:
AVERAGING TIME HOURS PER YEAR MAX o-2 HR X/Q IS EXCEEDED DOWNWIND DOWI NE. DIE rANCE SsCOR (METERS)
S 6116k.
SSW 6116.
SW "6116, WSW 6116.
W 6116.
P81W 61!6.
NW 6116.
TNNW 6116.
N 6116.
N"E 6126.
NE 6216.
E212 6116.
F 6116.
KSE 6116.
SE 6116.
$$E 6116.
MAX X/ý 0-2 HOURS
-2.87E-06 2.22E -06 2.6E -06 1.25E-06 1.13E-06 2.205E-06 1.23E-06 1.16E-06 1.13E-06
- 2. 05E06 1, 67E- 06 1.613-06:
2.87E-06 0-8 HOURS 1.265- 06 1.03E-06 1.21E-06 5,22 -07 4.84E- 07
- 5. 53E-07 6.05E-07 5.99E-07 5.48E 07 5.36E-07 5.01E-07 6.83E-07 1.01E-06 9.59E-07 7.68E- 07
- 7. 25E-07 8-24 HOURS 8.40E-07 6.963-07 8.132-07 3.38E- 07 3.15F-07 3.72F-07 4.29E-07
- 4. 17?El7.'
3.86E-:07 3 69E- 07 3.42E-07 4.83E-07 7.12E-07 6.54E507 5,20E-07 4 9s8Er0O I-4 DAYS
,3.45E-07
- 3. O1E- 07 3.45E-07 1.31E-07 I2 ý4E-07 1.57E-07 2.04L-07 1 90E-07 1.805-07 1.63E-07 1;49E-07 2.292 07 3.32E-07 2 85E-07 2.23E-07 2.04E-07 4.79E-07 0.00E300 41-30 DAYS, 9, 62E-0E 9.03E-01
- 1. 0,F-05
ý.3.25E-0O
- 4. 54E 06 6 1 98E-06
.6.0E-01 5.09E-01 4O55L-OO 1.115'--07
- 8. 60 +00 6.633-08 5.883-08 ANNUAL AVERAGE It 2.24E-08
,6.31E-09
- 9. 96E-09 1*88E-08 1.55 3-08 1.573-08:
1,06E-08 2.07E,308 2.89S-08 2.01 -08 1.505-081 1.28E.-08 URS AROUND SITE:
1SECZTR 42.7 23.8 35.4 4.7 5.3 6:.9 5.7 6.9 4.3 5-3 18.4 20.5 14.2 15-.I 223.7 SECTOR:
S ssw SW wsNw NW NNW NW NNWE NE ENE.
SE:
`9' 0'7 SRP 2.314 6116.
3.89E-06 1.73E-06 lil5E-06 SITE LIMIT 0.0OE+00 0.00E+00 0.03E+00 00.5 PERCENT x/Q TO AMI"INDIVIDUAL IS LIMITING, OX/Q VALUES (SEC/CUBIC METER)
FOR FUMIGATION AT THE BOUNDARY:
DOWNWIND DISTANC' FUMIGATION SECTOR (METERS)
X/Q S
- 6116, 2.223-05 SSW
,6116.
1.55F-05 SW 6116.
1:555-05 W
6116.
9-85E-06 Dl 611 6'.
9.853SS-06 WNW 6116.
9,85E-06 NW 616.
9.85E-06 Nw 6116.
9.953-06 NNE.
6116.
9.85E-06 NE 6116.
i.OiE-05 ENE 6116.
1.043-05 5 61.
1.343-OS.
553k 6116:
1,415-05 2-89E-08 2.89M-08
-.3 Page 32 of 45
Constellation NuclearServices:
Calculation No: NMPAST-O1-001 Rev. 2' Date: Dec. 19, 2003 SE 6116.
1.24E-05.
SSE 6116.
1.32E-05, ZrV N)D Page 33 of 45
Constellation Nuclear Services AUSNRC COMPUTER CODE-PAVAN, VEASION 2.C Calculation No: NMPAST-O01-001 Rev. 2 Date: Dec. 1.9, 2003 RUEN DATE: 09-03-02
/PiAET NAMtý NINE MILE POINT METEOROLOGICAL INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT:
60.7..METER TYPE OF GEESE ROUSND LEVEL RELEASE.
DELTA-T H.EIGHTS.: S.1.2., METER, SOURCE OF DATA:
JOINT FREQUENCY DISTRIBUTION-REPORT (JFD)
NINE :MILE POINT NUCLEAR STATION COMWENTS:ý NINE MILE POINT UNIT 1 REACTOR BUILDING BLOWOUT PANEL TO EAB/LPZ PROGRAMt
- PAVAN, 10/76, 8/79 REVISION, IMPLEMENTATION.OF REGULATORY GUIDE,1.i45 0
RErIVE ONCEN4TRAT'ON (X/Q)
VALUES.ASECACUBIC MET(RM VERSUS AVERAG:-NG. TIME HDURS PER YEAR MAX 0-2 HR.-X/Q.IS EXCEEDED DOWNWIND
- SECTOR, S
SSW WSw NW NNW N
NNE NE ENE ESE SE
$S8 MAX X/1 DISTANCE (METERS) 2000.
1500.
1200.
830.
830.
- 830, 830:.
830.
830.:
830.
a-3.0 830.
1900.
1900.
2300.
a06-*
0-2 HOURS 4.S98-05 6.34E-05
1.87E-04.
- 1. 83E-04 1.71E-04
- 2.01E-04
- 2. 1 0-4 i.95E-04
- 2. 34E-04 7.428-05
'S.448-05 2.978-03 4.11E-OS 2.34E-04 0-8 HOURS 2.48E-05 3.728-05 6.218-OS
'9.48E-05
- 1. 138- 04
- 1. 128- 04
- 1. 138-04 I,. 31E-04
- 1. 3SE-04,
- 1. 23E-04
,.1.46E-04, 1.4 SE-o4
,4. 26E-05 3.08E-05O 2.*23E-o5 8-24 HOURS 1 838-oS 2.84E-05 4.84E-05 7.35E-05 8.778-05 8.78E-0S 9., 158-05 I. 068-04
!9',
768-0S5 1.15E-04 1.19k-04 3.22E- 0S
- 2. 328-05,
- 5. 83E-.OS 6.63E-05 6.65E805
- 5. 92E-05 6.89E-05
- 7. 518-05 1.76F-05 7, 25F 05 6.218-06 8.438-06
3.4O8-05 3.338-05 2.'89E-05 3.30E-OS
- 3. 8783-05 7.438-06
- 5. 14E-Q6 2-41E.-.06 3.248-06 TOTAL HO 4.78E-05 0.00E+0.0 ANNUAL AVERAGE I1 1I.i28-06:
2.508-:06 4.99E-06 7.298-06 8.788-06
,9.448-06, 1.;388-05*
1.50E..0S, 1.438-05
- 1. 72F-105 1.73]E06 7,608-07
- 1. 019-,06 URS AROUND SITE:
N SECTOR.
4.3 6.8 28.0 32.8 28.4 23.0 27.3
- 36. 5:
28.7 43.7 41.0 7.3 6.9
.2_7 334.4 DOWNWIND
'SECTCR S
- SEP 2.3.4 830.
SITE LIMIT 00.5 PERCENT X/Q TO 4.44E-04
.0.008+0,3 A1 NDIVIDUAL IS 2.259-E04 C*
.008O
+00 L:MIT INC.
- 1. 72E-05 1.72E-05
ý(Al Page 34 of 45
SConstellation Nuclear Services iUSNRC COMPUTER.CODEwPAVAN, VERSION 2.0 Calculation No: NMPAST-01-001 Rev,2 Date:. Dec. 19,2003 RUN DATE: 09-03-02
/PLAINT NAME:
NINE MILE POINT METEOROLOGICAL INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT:
60.7 METERW TYPE OF RELEASE: GROUND LEVEL RELEASE DELTA-T HEIGHTS: 51.2 METER SOURCE OF DATA:
JOINT FREQUENCY DISTRIBUTION REPORT (JFD)
NINE MILE POINT NUCLEAR STATION COMMENTS:
NINE MILE POINT UNIT 1 REACTOR BUILDING BLOWOUT PANEL TO'EAB/LPZ PROGRAM:
- PAVAN, 10/76, DOWNWIND DISTANCE SECTOR (METERS)
S 6116.
- 6116, SW 6116.
WSW 6116.
W 6116.
WNW 6116.
NW 6116.
NNW 6116.
N 6116.
SNE 6116.
NE 6116.
ENE 6116.
E 6116.
ESE 6116.
SE 6116.
SSE 6116.
MAX X/Q 8j79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145
-RELATIVE CONCENTRATION (X/Q)
VALUES ($E$ /CUBICME.TER)
VERSUS AVERAGING TIME HOURS PER YEAR MAX 0-2 HR X/Q IS!
EXCEEDED 0-2 HOURS 1.31E-05 I.33E-05 1.81E*0S 2.07E-05 2.'74E-05 2.76 E-05
- 2. 54E-05 2.92E-05
- 2. 38E-05 3.03E05
- 3. 8SE-05 3.71E-05 2.31E-05 1.59E-05 9.24E-06 1.IOE-,5 3 85E-05 0-8 HOURS 5.96E-06 6.17E-06 E_.19E-06 E.99E-06 1.184-05 I.
.1E-05 1I.
- 1. 35E-05
- 1. 28E205.
- 1. 34E-05
- 1. 68E-05
. 68E-05 I.
.08E-05
.40E-06 4.38E-006 5.09E- 06 E-24 HOURS 4.03E-06 4.20E-06 5.52E-O0S
, 5.93E-06 7.70E-05 7.81E-06 7.96E-05
- 9. 12E.-
- .685-O'S 8'; 89E-05 1.11E-05 i.135-0O 7.35E-09
- 5. 055-05 3 -01E-06 3.45E-05 1.429-05 1.10E-OS 1-4 DAYS 1.72E-06 1.82E-06 2;34E-06 2,40E-06 308E-06 3.13E-06 3.44E-06 3_93E-06 3.73E-06
- 3. 66E- 06 4.49E-06 4.768-06 3.21E- 06 2.20E-06 1,34E-06 1.4 9E-06 5.69E-06 4.67E-06 4-30 DAYS 5.05E-07 5.51E-07
- 6. 572-07 8.27E-07 "8: 4"'07
- 1. 03E-06 1.17E-06 1.115-06 1.03E-06 1.23E-06 1.38E-06 9'.80E-07 6.68E-07 14.192-07 4 465-ý07 ANNUAL AVERAGE 1.13E-07 1.27E-07 1.51E*07 1.34E-07 1.65E-07 1.70E-07 2.365E07 2.67E-07 2.53E-07 2; 16E-07 2.51t-07 3.04E-07 2.29E-07 1.55E-07 1.01E-07 1.0 2E- 07
=N SECTOR 14.3 19.7:
24.1 30.;1 926
.8 20.5, 23.1 27.7 27.;9
.43.7 40.6 24.2Z
.19.7 13.;8
- .761.*7 DOWNWIND SECTOR S
NNE NE ENO EI ESE
-.0-TOTAL HOURS AROUND SITE SEP 23.34 6116.
5.C6E-05
.SITE LIMIT 3.58E-05 OTIHE FIV'2-PERCENT-FOR THE-ENTIRE -SITE X/Q 2,.17E-05 1.63E-05 IS LIMITING.
1,52E-05 1.37E-06
- 3. 04E-07
- 3. 04Eý07 9
Page.35 of 45
Constellation Nuclear Services IUSNRC COM>PUTER CCDE-PAVAN, VERSION 2-:0 Calculation No: NMPAST-01-001 Rev 2 Date: Dec.. 19i 2003 "RUN DATE: 0-03-02
/PbANT NAME:
NLNR MILE POINT METEOROLOGICAL ZNSTRUMENTAT1CN DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT:
60;7 METER TYPE OF RELEASE:
ELEVATED 130.8 METER DELTA-T HEIGHTS:
51.2 METER.
SOURCE OF DATA:
JOINT FREQUENCY2DISTRIBUT:ON REPORT WJD) IWINE MILE POINT NUCLEAR STATION.
COMMENTS:
NINE MILE POINT UNIT 2 MAIN STACK TO EA.*/LPZ PROGRAM:
PAVAN,,10/76, 8/79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.,145 0
RELATIVE CONCENTRATIQN (X/Q)
VALUES (SEC/CUBIC METER)
VERSUS AVERAGING TIME HOURS PER YEAR MAX o-2 HR X/Q IS EXCEEDED DOWNWIND SECTOR S
sew
.SW WSW ww W
WNW N
4NE NE ENE E
ESE SE SSE MAX X/Q DISTANCE (METERS) 2256.
1936.
1615.
1555.
1555.
1555.
1555.
1555.
1555.
1555.
.1555.
I3oo.
0-2 HOURS 2.19E-66
- 1. 79E-06 9.81E 1.05E7,06 1.07E-06 8.92E-07
- 7. 76E;-10 I. 864E-06 1.698-06 1.3iE-06 2.19E-06 0-8 HOURS.
- 8. IOIF-07 7.71E-07 3.3018-07
- 4. 508-07 3.45E-07 2.84E-07 5.138-07 7.,81E-07 7.84E-07 6.058-07 8-24 HOURS 6.45E-07 5.46E-07 4.83E-07 1.76E-07 1.60E-07 2.38E-07 3.00E-07 2.94E-07 2.15E-07 1.71E-07
.3.
538-ý07 5.40E.07 5.34*-07 4.73 3-07 4.12E-,07.
1P4 DAYS, 2,67E-07 2 31E-07 1, 75E-07 5, SOE-08 4.918-08
.8.
55E-08 1.218E-07
- 2. 11IE-07 177E8-07
- 3. 03E-.06 0.16E400 4ý30 DAYS:ANNUAL AVERAGE IN 7.49E-08 6.:ý75E8-08 4.06E- 08 9603E-08 9.028-09 1.94 E-08 3.27E-.08.
3--11E-0,8
ý3.07E-68
- 1. 75E-08 1.20E-08
- 4. 8"E-08
- 7. 64E-08 7.02E-08
.6.65.E-08 5.29E-08 TOTAL HOURS 8,. 65E-08 0.o oo+00
- 1. 59E:08
- 1. soF-O' 6.BOE-09 I,33E-09
- 1. 14E-09 3.25SE-.09 6.62E.09
SECTOR 43.7 22.3
- 32. 1 6.0 6.i 6.3 6.7
,7.0 6.1 5;.5 5.3 6;:1 16.6 21.9 13.6 225.9 DOWNWIND SECTOR S
WSW SW WNW N
NNE NE ENJ SE
,SSE
..3
- SRP 2.3..4 1555.
2.43E-06 1.09E-06 7.26E-07 SITE LIMIT o.O8+00 0..00E+00 GO.E0+00
- 00.5 PERCENT XiQ TO AN INDIVIDUAL IS LIMITINg..
0X/Q VALUES (SEC/CUBIC METER)
FOR FUMIGATION AT THEBOUNDARY:,
DOWNWIND DISTANCE FUMIGATION SECTOR (METERS)
X/Q S
2256.
- 2.36E-05 SSW 1936.
2.518-05 sw 1615.
2.90E-05 WSW 1615.
- 2.68E80-W
- 1555.,
.780 iN 555.
- 2.77E-05 NW 1555..
.2.77E-os
=4N isss:
2.77`-05 N
155s5.
2.77E-05 NNE 1555.
2.77E-05 NE 1555;.
2;78E-05
,ENE 1555..
2.808-05 8
.1555.
2.93E705 ESE 1555.
ý2.96E-0s 1.87E-08 1,87E-08 Page 36 of 45
i Constellation Nuclear Services SE 160o.
2.83E-05 SSE 2134.
2..2SE-05*
Calculation No: NMPAST41-001.
Rev. 2 Date: Dec. 19, 2003 N
-3 6"
.6 -c Page 37 of 45
Constellation Nuclear Services 1USN.RC COMPUTER CODE-PAVAN, VERSION 2.0 Calculation No: NMPAST-O1-001 Rev. 2 Date: Dec.,19.2003 RUN. DATE: 09-03-02
/PLANT NAME:
ýNINE MILE POINT METEOROLOGICAL INSTRUMENTATION DATA PERIOD: 1/01/97 TO.12/3i/oi WIND SENSORS HEIGHT:
60.7 METER TYPE. OF RELEASE:
ELEVATED 130,,8 METER
- DELTA-T HEIGHTS: S1.2 METER
'SOURCE OF DATA:
JOINT FREQUENCY DISTRIBUTION REPORT (JFD)
NINE.MILE POINT.NUCLEA STATION COMNENTSt NINE MILE POINT tUN:T 2, MAIN STACK 70 EABI/Lpz PROGRAM. PAVAN, 10/76, 0
8/7?9.REVISION, IMPLEMENTATION OF'REGULATCRY GUIDE 1.145 RELATIVE CONCENTRATION (X/ý)
VALUES (SEC/CUBIC METER)
- VERSUS, AVERAGING TIME HOURS PER YEAR MAX 0-2 HR.X/Q IS
.EXCEEDED DOWNWIND SECTORs SSW 5SW SW WNW NW 9NW NW NE NF ENE NE ESE SE SSE MAX X/Q DISTANCE (METERS) 6116.
6116.
6116,.
6116-.
6116.
6116.
6116.
6116.
6116.
6116.
6116.
6116.
.6116.
.6116.
,6116.
0-2 HOURS 1..73E2-06 1.49E-06 1.752-06 7.30E-0.7
- 798E-07
.8. 15E-07 8.102-0" 7.74E-'07 7.54E-07 6.93E-07 8.37E-07 1,43E-06 1ý28E 1.06E.-66 1.04E-06 1.75E-06 0-a, HOURS 7.79E-07 6.94E-07
- 8. 01E- 07
- 3. 25E-07 3.07E-07 3.59E-07 4.06E-07 3..,88E-07 3:76E-07 3.522E.07 3.19E-07 4.21F;-07 7.052-07 6.082-07 4.98E..07 4, 76E-07 8-24 HOURS S.22E-07O 4 75E-07 5.41:E-01 2.-09E-07 1, 99E-07 2.41E-07 2.86.E-01 2 69E-07 2.62E.-07 2.41E-07 2.17E-07 2..992*07 4.95E-O-4.198-.07 3.41E-07 3.229-07 1i-4 DAYS 2.20.-07 2.08E.-07 2.31E407
- 8. 092-0ýO8 7.75E-08 1;34E-07
- 1. 21E-07
- 2. 30E-07 1.50E-07
- 2. 3.9E-07 0, OOE÷00 4-30 DAYS ANNUAL AVERAGE IN 6.33E- 0
- 6. 35E-08.
6.82E-08 2;.06E-08 2.. 92E-08 3.86E-08 3.89E-08' 3.2:2E- 0E 2 7.80E-0E.
5.852E-0E
'4.622-01E
-4.06E-06
- 1. 382-08 1.49E-08
- 1. 532-0 3.8 8E.;
09 6'.4E-09 1.2 E-OS 9.520-09:
9,846-09 7.5 3E-09 1.31E-08
- 1.4 16-08 1.09,E-0 9.13E-09, SECTOR 42*.1 30:i:
43.7 7.3 7.8 7.7.
7:2 7.0 6.7, 2,6.8
.191.6 16.7 15,3 261.7 DOWNWIND SECTOR S-4~
wsx NW NNW ENE NE ESE SE SSE p
.4, TOTAL HOURS AROUND SITE:
SRP 2.3.4 6116.
2.i9E-06 1.01E-06 6.83E-07 SITE LIMIT 0.00E+00 0.00E+00 0;OOE,+00 00.s PERCmiT.X/Q TO AN INDIVIDUAL IS LIMITING.,
OX/Q VALUES (SEC/CUBIC METER)
FOR FUMIGATION AT THE BOUNDARY:
DOW14WIND,DISTANCE FUMIGATION SECTOR (METERSj X/Q S
6116..
3.426-OS SSW 6116.
1.15E-05 SW 6116.
I.15E-05
.WSW,
.6116.
8.04E-06 N
.6116.
$.04E-06 WNW
- 6116, 8.04E-06 NW 6116.
8.04E-06 NNW 6116.
8.04E-06 N
6116.
.40 NNE 616.
8.04E-L06 NE 6116..
8.23F-06
- ENE 6116.
8.42E-06 E
.6116.
1.02Eo05 ESE 6116.
1.06i,-05 8.76E-06
- 0. 0OE+00 4.99E-08
,1.992- 08 cJ~,
Page 38 of 45
IOConstellation Nuclear SErVices SE
- 6116.
9.664E-o6 SSE 6116.
1.01E-OS Calculation No: NMPAST-01-001 Rev. 2 Date: Dec. 19, 2003 -
Page 39 of 45
C onstellation Nuclear ServiceS IUSNRC COMPUTER CODE-PAVAN-., VERSkSIO 2.0 Calculation No: NMPAST401-001 Re. 2 Date: Dec. 19, 2003
.RUN DATE: 09.-03-02
/PLANT NAME:
NINE MILE POINT METEOROLOGIcAL INSTRUMENTATION DATA.PERIOD: 1/01/97 TO 12/31/011 WIND SENSORS HEIGHT: '60.7 METER TYPE OF RELEASE: GROUND LEVEL RELEASE DELTA-T HBTGHTS: 51.2 METER SOURCE OF DATA:
JOINT FREQUENCY DISTRIBUTION REPORT (JFD).
NINE MILE POINT "NUCLEAR STATION COMMENTS:
NINENILE POINT UNIT,2 COMBINED 'RADWASTE/REACTR BUILDIN3 SVENT TO EAB/LPZ PROGRAMi PAVAN,"/*76.,
8/79 REVISION, IMPLEMENTATIONI OF REGULATORY GUIDE 1.145 RELATIVE. CONCE4TRATION (X/Q)
VALUES (SEC/eCUBI M3TER)
VERSUSl AVERAGING TIME HOURS PERYEAR MAX 01 2 HR X/Q, is EXCEEDED
- DOWMW INr
.SECTOR S
NW NNW
-NNW,N IUNE NE ENE E
ESE SE
,SSE MAX X/Qý DISTANCE (METERS) 1945.
1695.
1381.
1381.
1381.
1381.ý 1381.
1381.
1381.
1381.
13t81.
.1686.
1686.
1743.
2094.
0-2 HOURS 4.65E-05 5;47E-05 9.14E-05 1.10E 04 i _10E_04 1.02E-04 1.16E-,04 I.24E-04 11 717E-04 1.42E-04 1.34E-04
- 8. OOE-05 6.,22E.-os 4_.07E-05
- 3. 85E-05 1.42E-04 0 -
HOURS 2.51E'-05
- 3. IOE-05 5.13E-05
- 6. 16E765 6.25E-05 6.28E-05
- 7. 3.38E-.05 6.86E-65
- 8. 118E-05 8.ý 1:3E -0 s 4.70E OS 2.32E.,OS
- 2. OSE-05 8-24 HOURS 1~.
85F-05 2.34E-05 3.91E-ýOs
- 3. 85E-,05 4.71E-0-5 4-.91E-05 5.76E-05 5.,25E-05 6.22Ew0S 6.342-'05 3.60E~-05 1.75E-D5
- 9. 97E-05
- 0. 60E+00 1-4 DAYS 1,27E-O5 2.18R45:
2.06E-05 2.,46E-65
- 2. 55E-015 2.89E- 0 5 3.21E-05
- 2. 94E-0S 3.42E-05 3..69E-05 9.54E-06 5.21E-O5 0.0 OEi00 4-30 DAYS, 3.62E-06 9.46E-06, 8.38E--06:
1.60E-05 1.35E-0-E
,I.48E-05
ý1.46E-05.
- 1. 27E 1. 45E-05.
- 1. 70E-0S, 8.85E-06 6.23E-06 3_.89E706
- 2. 84E-0O:
TOTAL A0 2.0SE-05 0.OOE+00 ANNUAL AVERAGE IN
- 1. 12E -,6 l..79E-06 3.40E-06 2.79E-06 3,33E-06
ý3.59E- 06 5.31E-06, 5ý.73E-06 4,59E-06'
- 5. 1OE-06 3.22E-06
- 2. 16E-06, 1,:36E-:06 8.548-07
)URS AROUND SITE:
,SECTOR 1 0.3 13.1 24ý.4 27,1 3i.7i 28.1l 21.8 21.4 34.9 27.5 43.7 20.6 17,9 11.8 9.9 383.5 DOWNWINDJ
- SECTOR.
s sS1W WSW W
WNW NW NNW.
N NNE NE ENE E
ESE SE.
-Z SRP 2.3.4 138,1.
SITE LIMIT 00.5 PERCENT XIQ TO AN4 2;438-04
- 0. OOE+00 INDlIVIDUAL 1S
- 1. 34E-04 O.OOE+O0 LIMITING.
6.56E-06
- 6. 56E- 06
.4 14r Page 40. of 45
C onstellation Nuclear Services IUSNRC C0O4PUTSR CODE-PAVAN, VERSION 2.0 Calculation No: NMPASTO10-001 Rev. 2:
Date: Dec. 19, 2003 RUNODATEi-:
09-03-02
!PLANT NAME:
NINE. MILE POINT.
METEOROLOGICAL INSTRUMENTATION' DATA PERIOD: 1/01j/97 TO 12/3*/01 WIND SENSORS HEIGHT:
60;7 METER TYPE OF RELEASE: GROUND LEVEL RELEASE DELTA-T HEIGHTS: 51.2 METER SOURCE OF DATA:
ýJOINT FREQUENCY DISTRIBUTION REPORT (JFD)
NINE MILE POINT'NUCLEAR STATI.ON
- COMIENTS NINE MILE POINT UNIT 2 COMiNED IRADWASTE/REACtOR BUILDIN3 VENT TO EAB/LPZ PROGRAM:
- PAVAN, 10/76, 8/79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145 RELATI.VE
,CONCEIITRArION (k/Q)' VALVUES OFEC/C d.XC METER)
VERSUS AVERAGING TIME HOURS PER YEAR MAX
,0-2 R X/Q IS EXCEEDED DOWNWIND SECTOR s
SSW sW
.WSW w
WNW
.uIW NN irNE
.NE Em1 E
- MAX.!
xQ DISTANCE (METERS) 6116.
6116.
6116.
6116-6116.
6116.
6116.
'6116.
6116.
6116-61 16 6116.
611i6.
6116.
0-2 HOURS 1.30E-05 1.2E-05 1.81E-O5 2:407E-05 2.74E-05
- 2. S4E-05 2.92E-05
- 2. 78E-05 3.603-05 3..85?-D5 3;71E-05 2.31E-05 1I 58E505 9.24E-06 1.1OE-0s 3.85E-05 0o-HOURS 5.90E,65 6.11E-06
- 8. 92R-06 1.27E-015
.. 18E-05
!1.
17505 1.345-05 1.272-05 1.33E-O5 1.66E-05 I:.67E-05
- 1. 07E05 7;32E106 4.36E-06 5.06Ek06 8-24 HOURS
- 3. 98E-OE 4.15E-06 5.47E-*OE 5.:86E-06 7.61E-06 7.72E-06 7.892-06 9.*032-06 8.80E-06 1.09E-05 1.12E20OS 7.28E-06 4.ý 98E-06 2.99E-06 3.428-06 1.40E-05 10.9E-05 1-4 DAYS
- 1. 69E-066 1.79E206 2..30E-06 2.36E-06
.3.07E-06 3.39E2-06 3.86E-06 367E-06 3.60E-06 4.39E-06 4.68E-06 3:16E-06
.2.16H-06 1.32E,06 1.472-06 5.552-06 4.59E-06 4-30 DAYSý 4.-. 92E-07 "5.3 72-07
!6.66E-07 6.37E-07 7.99E-07
- 8. 19E-07
.'-. 01E- 06 1'. 14E-06 9.98E-07
- 1. 192-06E
.9.56E-07 6.505-0T
- 4. 1.E-07
- 14. 3S-.07, TOTALNHO
- 1. 33E-06 ANNUAL -AVERAGE I1 1..
i.09E-o0-1.23E-07
,.462-07 1.29,E-07.
,1.57E-07
,1.63E-07"
'2.2 9E-07
.2,57E,-07
- 2.439-07 2.'.082-07'
- 2:.40E-07*
.2".93E-07 2.21E-07 9.80E-08ý 9.83E-08 FURS AROUND SITE:
N SECTOR 14.3 342.7 1.9.
7, 24.1 30.1 26.8 20.5 23.1 27.7 27.9 43.7
- 0.
24.2 19;7 12.8 13;8 761. 6 DOWNWIND SECTOR sSý
,SW.
t4W N.
NW
- NNW, N
NNE NE ENE E
.4, u SRP 2.3.4 6116.
4.99E-05 SITE LIMIT 3.53E*05.
0THE FIVE-PERCNT-FOR,-THE-ENTIZ2-S!TE 2.13E505
- 1.
- 62E-05 X/Q it LIMITIkG.
.2.932-07
,2.93E-07:
Page 41 of 45
w ZýI C_ý.7'1(0- ý +
Consteliation SNuclear Services 417
ýCalculation No::NMPAST-01-001 Rev. 2 Date: Dec; 19, 2003 Appendix C - Listing of Files on DATA CD-ROM for Calculation NMPAST-01-001 Page 42 of 45
SConstelatien Nuclea Serpices Calculation No: NMPAST-01-001 Rev. 2 Date: Dec. 19, 2003 Note: This directory listing -does not includethe calculation document,, cover page-and review checklist files.
D irecto-y of D;\\
08/05/2002' l:04 AM 08/23/2002 11:.15 AM 20,992 Terrain Heiqht Estimates.xls 58,368 Revised NMP 60m JFD 1997-2001 for CNS doc Directory of D:\\0.5% Sector Dependent Calculations 12/19/2003 12/19/2003 08/29/2002.
08/28/2002 o9/08/2oo2 08/28/2002 12/1/z20o03 08/28,2002 08/28/2002 08/20/2002 12/19/2003 08/28/2002 12/19/2003
.08/28/2002 09/06/2002
.08//2'662
.8/28/2002 08/28/2002 12/1,9/2003 08/28/2002 08/28/2002 08/28/2002 08/28/2002 09/06/2002 08/28/2002 08/26/2002 08/28/2002 08/2 8/2002 U8/P a/20U2 05:0G PM 05:00 PM
.08:34 AM 07:54 PM 10:03-AM 07:56 PM 01:55 PPM 08:10 PM 08:14 PH.
08:IS PM
<DIR>
<DIR>
331,264 332,288 331, 264 331,264 332,288 331,776 331,264 329,728 1 'Main U1 Main U1 Beah
- 01. main 01 Main UI Main U1 Main U0. Main Stack Stack Stack Stack Stack Stack-Stack Stack to to LO to to to to to EAB EAB
- EAB, LPZ LPZ LPZ L;Pz ESE.)iq SSNXls ESE. x1s SW. x l1 WSW, X.s~l 03:48P PM 08:18 PM 03:43 PM 08:21 PM 10.40 AM O182 PM 08:25 PM 08:34 PM 08: 35. PM 01:55 PM 08.: 37 PM 08:39 PM 08:40 PM 08:42 PM 10::53 AM 08:28 PM 08:29 PM 08:.30 PM.
08:31 PM 08:33 PM 28 File(s) 333,312 U1 Reactor BLDG Blowout Panel to 331,264 U1 Reactor BLDG Blowout Panel to 330,752 U. Reactor BLDG Blowout Panel to 332,288 01 Reactor BLDG Blowout Panel ro 332,288 U! Reactor BLDG Blowout Panel tO 332,288 U1 Reactor BLDG Blowout. Panel to 331,264 U1 Reactor BLDG.Blowout. Panel to 3:32,288 U2 Combined Radwaste and Reactor 331,264 U2 Combined Radwaste and Reactor 332,288 02 Combined Radwaste and Reactor 332,289 W2 Combined Radwaste and Reactor 332,,800 U2':Combined Radwaste and Reactor 331,28R U2 Combined Raduaste 'and Reactor 331, 264 U2' Combined Radwaste and Reactor 332:.288 U2 Main Stack to LPZ -. ESE.xls 331,776 U2 Main Stack:to LPZ - S.xls 331,776 U2 Main Stack to LPZ -
SE.xls 331,264 b2 Main Stack to LPZ '- SSE.xls 331,264 U2 Main Stack to LPZ SW.xls 329,728 U2 MAii SLauk Lu LPZ WSW.xls 9,28.7,168 bytes EAB E..xls EA S.xls EAB WSW.xls LVZ -
SSW~xls LPZ SW.Xls BLDG Vent to EAB BLDG Vent to EA' BLDG Vent to EAB BLDG VeýI Lu LPZ BLDG.Vent to LPZ BLDG Vent to LPZ BLDG'Vent,-:to LPZ SSE.xls SSE.xls SSW-xlr SW. X1s
- Directory of.::\\5%
Site'. Limit Calculations 121/19/2003 12/1 9/O003
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- 12/I 9/2003 12/19/2003
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.12/19/2003 12./1 9/2003
.12/,19/2003
.044: 32 PM':
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04:21 PM 3i,603,456 5% Envelopes.xls 04:32 PM 16,3.84 Intermediate Time 'Calculatins-.xls
'04 z19 PM 359,93G Unit 'I, Main Stack to, EAB.x1r 04:19 PM 367.616 Unit.1 Main Stack toILPZ.xls 04: 20 PM
'354,304 Unit 1 Reactor BLDG Blowout Panel to EAB.xls
'04:20 PM
.355,840 Unit 2 Combined Radwaste and Reactor BLDG'Vent to EAB.xls
.04:20 PM 3172,736 Unit 2 Main Stack to EAB'.xls 04ý.:20 PM 3.69,664: Unit.2 Main Stack to LPZ.xls 8 File (s) 5,,799,936 bytes Directory of D0\\Input Files 11/18/2003 11/18/2003
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,<DIR>
7,913 7,441 7,441 7,913 7,442 7,444 Unit Unit Unit unit Unit Unit 2
,2:
Main' Stack to 'EAB and.LPZ.inp Reactor Bldg Blowout Panel to.EAB and,,LPZ. inp Turbine Bldg Blowout Panel~to EAR andL.nPZ.inp Main :Stack 'to 'EAB and LPZ.inp Main Steam Tunnel to EAD and LPZ.inp Post Accident Samp to EAB and LPZ.inp Page 43 of 45
N ruConstellation Nuclea Ser~vices Calculation No: NMPAST-O1-OO0 6Rev.
2 Dateb: Dec. 19, 2003 I8/26b/UU2.
10:04 AM 08/26/2002 1.604 AM 8
File.je) 7,450 'Unit 2
.7,448 Unit 2
,60,492 bytes R'edCCL1 Bldg to EAB. and LPZ..inp, Stby Gas Bldg to EAB and LPZ.inp Directory of D:\\Maximum.Stack XQ..Distance 11/18/2003
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andc 250.inp, 7,913 1000 and 1250..inp 602,588 1000AN-1.out 598,239 100.AND-1.out 7,913 15060 and 1750.inp 604,359 1500AN-I.Out 7,9.13 2000 and 2500.4np 605,411 2000AN-1.out 7,913 3000 and 350O.inp 60oo,698o3000AM-1.out 7,913 4500 and 5000.inp 61S,621 4ý500ANL,but 7,913 500 and 750..inp 597,141. 500AND..-IOat 7,913 510. and 35..inp 596,977: 51OAND-i..Out 7,913 525 and 550.inp 596,679' 525AND-i.out 7,913, 5500 and 6000.inp 615,867 550OAN-I.out 7,-913 600r and 650.inp 595,555, 600AND-I..out 7,913.6500 and 7" 0.oinp 617,663 6500AN-1.out 7,913, 700 and 850-inp 597,491 -00AN)-I.OUt 7,i..911 8000 and 9000..inp 602,625 8000AN-I.,out 224 run. unitl..bat 129,536 Unitl Max:.Stack XQ 8,:696,456 bytes (Scoping).xl's Directory of D:\\Maxifmum Stack XQ. Distance.vnit 2
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- I50.OAN-1. oUt 2000 and 2500.inp 200oAN-1.out 30060 and 3500.inp 3000AN-l.out 4500 and.5000.inp 4500AN-I.out 500 and 750.inp 500AND-I.out 510 and 535.111p 510AND-1.out Page. 44 of 45
ConstefSation Nuclear Services Calculation.No: NMPAST-01-001 Rev. 2 Date: Dec. 19,12003 08/27/2002 08/2,7/2002 08/27/2002.
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-7;913. 525 and SS6..inp 598 435 525AND-I.out' 7*.913 5500 and 6000.inp 616,055 55,00AN-i.out 7,913 600 and 650.inp-598,117 600AND-I.out
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.913, 8000 and.9000.inp 607,754 8000AN-*1.OUt 224 rUnunit2.. bat 130,048 Unit 2 Max Stack XQ' 8,708,967 bytes qScoping).x-s DireeLr CD:Otu Files
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Calculation Cover Sheet
,Calculation' No0 -N AST-02-001 Rev.
2, Nb. of Pages 37 Titlo Alculation of Attmogheric Disp*.*. jo Coeffiientis',
att t NM,jUit 1 Technical Srolort Center and Units I and 2 Contro Room Intakeshfor Al Releases Rev- 0 Name Signture.
Date____
Preared B Shane Gardner Ap rov By TaraNeider Rev. 1I..
Name Signature Date
- d.
ShaneGardner Checked By James Heffner...
Approved By Tara Neider Description of Changes 1This calculation revision is in response to the availability of revisednmeteorological data from NMP. Thiisarevision incorrates the results of the revised meteorological data into the body of the calculation, i.e. the X/Q.resbults in Tables 3.3.3 and 3.3.4 have been reculated with the new meteorological data. Also; this revision adds the calculalion of X/Q.values at the-Unit I Technical Support-Center,This revisio furth incudes changes to, resolve minor editorial issues.
AffecedPages, Calculation f0ver Sheet..(Titlý;, all~page thqqev Rev.2 2
.Name SI 7':"]'gnature Date C hacked By
".D avid M atchick i 1 *.zc * * -~/.
.: * -/ i -
L vcl B y,,,f,:,,
77 1,3io
'Descption of:Changes
ýz, I
Th-prpose: of this revision is to respond to commentsmade in a third party review performed by NISYS Co.rp. at fte request of NM
$NS. Several comments were made ad the reader is refered to the NISYS documet NISYS-] 169-DVGO I/RO for more, detail. CNS and NMPNS agreed to a plan to resolve a selectionof the.NISYS comments(see. CNS.-03-218, 9/24/03 and electronic correspondence from Timothy M.Kutz to Shane Gardner, November 6,2003, "Re: CNS Comments on NISYSRevierw of X/Q Calculations"). CNS-03-218 provides a descripftion regarding how the commnents. were addressed and provides the basis for inrcaqnating th comments Mo this ealculaon. More specifiaIly, theltobItowin
.comments were addressed:
rNISYS Commer
ýNo.
Ab 2u,*
Description
- Include a scale drawing (compass s'rose")
s't
'atCeMedoCUxnutingconformjanceto Safety Guide 23
,first part only. iustification of assumpitions Affecte Page(s)
Appendix A 4,26 (Rels.,29 &30) 8-10 CNS OA Form: OA-3'2:.1, Rev 0
4a" hicorrecttconversions from Engigs to metric units 5a add a detailed listing of files on Cbe provided 6,86,16-19,22-24 Appendix'D Only comment 4a impacted the results ofthe calculation. This conunent chanlgd building wake area input
,parwnetds fbrseveral ofthe ARCON96 cmpuitr rins: and tbrefore impacted IheOX/Q estimates. The:
revised results were compared against the previous results firom. revision 1. ofthis calculatiom. It was dcterened ihat the previous revision I results wr oevative and bounding wita pe to-the revis results., Most of tho changes in the XQ values occurred for XfQs at theAJnit I Control Room intake. The ofllowing is a catalogue of the changcs in the X/Q Valuesh:
Release Point
,Unit I Reactr Bldg.
Unit I TurblneBldg.
Unit I Main Stack:
unit 2 Combined Radwaste/RxVent
-Unit 2 PASS Panel:
unit 2 SGTS Bldg Unit 2 Main Steam Tunnel Unit 2 Main*Sta ck Unit 2 Main'Stack Unit 2 PASS Panel Unit 2ISGTSBldg.9 Unit 2 Main Stack.
Receptor Pojnt UnitA Control Room Unit,[ Control Room Unit 1 Control Room U*nit'l ontrol Room Unit.I Control Room Unit I Control
.oom.
Unit I Control Room niut-I Control Room Unit I Tech. Support Center 1Unit 2 Cýntrol Room
'unit 2 Control Room Unit 2 CoITrol Room AveOnj Change in X/Q (')0
-4.1'
-2.A
-1.4
-4.4
-I.S
-0.3
-0.2
-01
-03 In addition to the changes indicated above, the calculativ* was further revised to incorporate minor editorial changes.
Affected Pages: Cadculation Cover SheeLt(Tite): all nones thereafter I
Calculation Review Checklist Circle.as anpropriate. the Yes/No/NA for all items Correct calculation format............................................................................
J N o/ NA Correctness of assumptions............................................................................. (O* o/NA Adequacy of assumption basis.............
4.No/NA Correctness of parameters used.......................................
(:.
No/NA Appropriate choice of method............
Y o/NA Adequate documentation of method....
6YoNA Correct application of method.............................
o/NA Correctness of results/conclusions..............................................
,.o...
Adequate Reference'list:...............................................
o/NA If computer software was used to perform the calculation, the following elements shalll also be considered::
Proper sofwar verificationand verification documentation.......................... O No/NA Corre-tness of input parameters........................................................................
( 9 No/NA Correct information in analysis calculation es 0/A Correct interpretation of results....
N, NA Smgnature:
Dale____________
64S GA Form: QA-3.2.2. Rev. 0
-53 a
Calculation No: NMPASTi02-001 Ste T Rev. 2 Nucle Services Date: December 22,,2003 Table of-Contents
- 1. Objective......................................................................................
2. Background
4.............
!,.k
.4 2.1. Applicable Regulations and Commitments..................
....................... 4
- 3. Methodology.....,................................................................................
4'
- 4. Computer Hardware/Software Usagel........
4.1. Description of Hardware Used...........................
5 4.2. Description of Software Used....
5 4.2.1. Software Verification..................
...... 5
- 5. Inputs....,,...,
,...................... 5 5.1. Meteorological Input...................
5 5;.2. Release/Intake Distances and Directions...................................
I
..5 5.3. Release/Intake Elevations
- 6 5.4. Building Dimensions Related Pertinent to Wake Area Calculations.......................... 6
- 6. Assumptions...........
8
- 7. Calculations and Results..............................................................................................
10 7.1. Release/Intake Distances and Directions Calculations*..................
10 7.2. Building Wake Areas.............................................
16 7.3. X/Q Values...........................................................
20
- 8. Conclusions................................................................
.... 25"
- 9. References....;.....................................................................................,25 Appendices...................................................
27 Appendix A - Site Plan Showing Associated X/Q Directions.....................
28 Appendix B-Representative ARCON96 Input File..........................................................
29 Appendix C - List of Computer Runs.....................................
30 Appendix D -;List of Files On CDROM............................................................................
32
Co.s........Calculation No: NMPAST-02-001
,OConstellatio Rev. 2 NuctearServices Date: December 22, 2003
ýList of Tables Table,5.2.1,. Releaselintake Distances and Directions.....
6.............
...... 6 Table 5.3.1. Releasellntake Elevations.... ;.............
8 Table 7.1.1. Summary Tableof Calculated Coordinates of Release/intakes:Locations for Units 1 and 2 13 Table 7.1. 2. Summary Table of Distances and Directions for Various Releases to Unit 2 Control Room Intakes...............................
.................... 14 Table7.1.3. Summary Table of Distancesand: Directions of Unit 2 Releases to the Unit I Technical. Support Center................................................
... 15 Table 7.2.1. Calculated Building Wake Areas................................
19 Table 7.3.1 ARCON96 Distances and Directions Input.........................
21 TableT7.3.2. List of CommonlDefault Input Data to ARCON96........
i.........
22 Table 7.3.3-1. X/Q Values for the Unit I Control 'Room...................................................
23 Table 7.3.3-2. XIQ Values for the Unit 1 Technical Support Center...................................
23 Table 7.3.4. X/Q Values for the Unit 2 Control Room...
................. 24 Table C-I. List of Com puter Runs....................................................................................
30 Page 2of 37
Constellaton Nuclear Services.
Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Listof Figures Figure 7,1.1. Schematic ofCoordinate Used In Calculating Releaselintake Distances and Directions............
........................................................................................................... 12 Page.3 of 37
Constellation Calculation No: NMPAST-02.001 Rev.2 NuclearServices Date: December 22,2003 1,. Objective The purpose of this calculation-is to determine conservative estimates of atmospheric
,dispersion coefficients (X/Q) for the Nine Mile Point Unit 1 and 2 Nuclear Station control room air-intakes for release pointsdefined herein.
2. Background
Nine MilefPointNuclear Station (NMP) hasrequested the services ofConstellation Nuclear Services'(CNS) to evaluate and update offsite-and control room atmospheric dispersion
.coefficients for, Units 1 and 2. The atmospheric dispersion coefficients (X/Q) are needed for a scoping study to determine the feasibility of the use of Altemative Source Term (AST) methodology for the determination of design basis accident dose consequences and can be applied to other calculations which, determine :radiation dose consequences at the Unit-1 and 2 Control Rooms, 2.1. Applicable Regulations and Commitments This calculation employs the ARCON96 computer code (Ref. 2) to:.calculate XIQ values. The Regulatory Guides (RG) 1.145 (Ref. 3) and 1.183 (Ref. 4) are utilized to,perform the analyses herein. Other regulatory guidance on atmospheric relative concentrations for *Control Room radiological habitabilityassessments (Ref-5) has been implemented as necessary. The regulatory guidance foranalyses associated with the useof AST is found in RG 1.183 (Ref. 4).
Meteorological data are hourly averages obtained from NMP Joint Frequency Distribution
.Report (JFD) (Ref. 29) and the analysis conforms to the requirements, of R.G. 1.23 (Ref.30).
- 3. Methodology Recently published guidance (Ref. 4 and 5) has outlined acceptable procedures for calculation
,of X/Q values With the computer code system ARCON96. ARCON96 employs a straight-line Gaussian dispersion model to calculate X/Q values based on hourly meteorological data. The X/Q values calculated are ýhourly, normalized concentrations. These values are then averaged to provide X/Q values for time periods ranging from 0 to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />. A more complete discussion, including details on the methods, input guide and programmer's guide, are provided in'the user's guide (Ref. 2).
The ARCON96 computer.code was utilized to calculate conservative estimates of the XIQ values for all releases to eachof the NMP Unit 1 and 2 Control Room intakes and the.Unit I Technical Support Center. The recently published guidance (Ref. 5) was reviewed and used as appropriate. Moreover, the details pertaining tothe use of ground level, vent and stack
- releases, calculation of building wake correction factors, appropriate ARCON96 default input and the use of diffuse area sources were considered for inclusion.
Page 4: of 37
Calculation No: NMPAST-02-001 ConstellationRev.
Nuclear Se**ies Date: December 22, 2003
- 4. Computer Hardware/Software Usage 4.1. Description of Hardware Used Allcomputer calculations were performed on Windows 98 and Windows 2000 personal computers. The computer identification of the PCs used are CNS-1:15 and CNS-1 12.
4.2. Description of Software Used The ARCON96 computer code system was used to calculate control room X/Q values.
ARCON96 is an:NRC affiliated computer code which implements a straight-line Gaussian dispersion model to estimate downwind X/Q values. The X/Q values are determined from hourly meteorological data. ARCON96 has the capability to calculate ground-level, vent or stack release scenarios. A complete description of the code, including its capabilities, technical basis and programmer's guide can be found in the user's guidef(Ref.2).
Microsoft Excel was utilized to calculate distances and directions for release/intake scenarios bnot readily available by reference.
4.21..
Software Verification ARCON96 has been verified and validated (Ref. 6) in accordance with Quality Assurance procedures (Ref. 7). Microsoft Excel is classified as.Category 3 Software per section:3.2.3 of the CNS Computer Code Verification 3.5 (Ref. 7) and does not require initial verification.
The results obtained from use of Microsoft Excel wereverified in the same manner as technical reportsW(Ref. 7).
- 15. In puts 5.1. Meteorological Input
- 1. Upperleveliwind measurement height = 1199 =.60.66 meters (Ref. 8)$.
2, Lower level wind measurement height = 31' = 9.45 meters (Ref. 8).
3.1 Meteorological input data provided in ARCON96 MET file "NMP: 1997-'2001 ARCON96 Rev 1.txf (Ref. 27). This data is a revision to previously used data (Ref. 9). This file has been renamed "NMPRi.MET" and is included ýon the attached disk.
5.2. Release/Intake Distances and Directions Distances and sector bearings for the various releases:for both Units I and 2 are provided in several previous calculations performed by Meteorological Evaluation Services (MES), Inc.
Table 5..2.1 summarizes this input data.
Page 5 of 37
~+2~t Constellatio, Nuclear.Services Calculation No: N MPAST-02-001 Rev. 2
- Date: December 22, 2003 5.3. Release/intake Elevations Elevations for the release and intake points are provided in various MES calculations, USAR and drawings. Table 5.3.1 summarizes the, elevations of the release andintake points. Unless otherwise indicated, the elevations listed are:above plant :grade.
5.4. Building Dimensions Related Pertinent'to Wake Area Calculations Unit 1 Turbine Building
- 1. Building height above grade= 369` 3 1/2"- 261' = 108`3 1/12 = 33 meters (Ref. 10).
Unit 2 Turbine Buildina 3.
East-west dimension = 338' = 103.02 meters.(Ref. 1 ).
North-south dimension = 140' = 42.67 meters (Ref. 11).
Building height above-grade := 1,20' =36.58 meters (Ref. 12).
Unit 2 Reactor Buildinq 1.
2.
Outer radius = 85'.6" = 26.06 meters. (Ref; 13)
Maximum wall height above grade (top of parapet) = 430' 1 1/2"- 261' = 169' 1 1/2";
51.55 meters (Ref. 14).
Table 5.2.1. Release/Intake Distances and Directions Releaselintake
- Distance fDistance Sector Reference I(ft.)
(I )
Bearing()
Releases to Unit 1 Control Room Intake
.Unit 1 Reactor Building Blowout Panel"2' /Unit 1 340 103.6 149W SSE Table 1 Control Room Intake.
_Ref.
18
.,Unit -1 Turbine Building Blowout Panel'2' / Unit 1 236 71.9 1170 ESE Table 1 Control Room Intake Ref. 18 Unit I Main Stack/.Unitl Control Room Intake 400 121.9 166" SSE Table 1 Ref. 18 Unit 2 Combined Radwaste & Reactor Building 615 187 2460 WSW Page 2 Vent-Unit 1 Control Room WSW Ref. 17 Unit 2 Main Steam Tunnell/Unit 1 Control. Room 595 181.
246°WSW Page 2 Ref. 17 Unit 2 Standby Gas Treatment System Building / 800 244 2420 WSW Page:2
{ Unit 1 Control Room Ref. 17 "Unit 2 Post-Accident Sampling System Panel./
.660 201 230° SW Page 2 Unit 1 Control Room Ref. 17 Page 6 of: 37
1+I t~
i~c4 constellati n
SNuclear Services Calculation No: NMPAST-02-001.
Rev. 2
,Date: December 22, 2003 Releaselintake Distance Distance Sector Reference.
__ft_) _(m)
-Bearing111 Unit 2'Main Stack /'Unit I Control Room 1355 413 2330SW Page 2
_____Ref.
17 Reieases to.Unit i Technical Support Center Unit 1 Reactor Building Blowout Panel t 2 /Unit 1 343 104.5
- 86) ESE Table I Technical Support Center,._,
Ref. 18 Unit 1 Turbine Building Blowout Panel'2' / Unit 1 328 100.0
- 86. E Table, I Technical Support Center
- Ref. 18 Unit 1 Main Stack Unit 1 Technical Support' 330 100.6 1400 SE Table I Center-Ref. 18 Releases to Unit 2 Control RoomIntakes Unit 1 Main Stack l Unit2.Control Room West-740 225.6 121.5" ESE Table 1 High Ref. 18 Unit 1 Main Stack /Unit 2 Control Room West-720
- 219.5 119.5" ESE Table 1 Low
- Ref. 18 Unit 1 'Main Stack,. Unit.2 Control Room East-800 "243.8 115 7 ESE Table 1 High Ref. 18 Unit I Main Stack,/Unit 2 Control Room East-800 243.8 1150 ESE Table 1 Low
- Ref..
18 Unit 2 Main Stack/ Unit 2 Control Room West-937 286 2250 SW Table 4..
High Ref. 16 Unit 2 Main Stack Unit 2 Control, Room West-919 280 S
225SW Table 4 Low Ref. 16 Unit 2 Main Stack / Unit 2-Control Room East-843 257 202.50 SSW Table 4 High
'_Ref. 16 Unit 2 Main Stack /Unit 2 Control Room East-846 258 202.5* SSW Table 4 Low.
R ef. 16 Notes.,
- 1. Sector bearing in-degree is measured relative to true north.
- 2. Distance and directions from midpoint of blowout panel.
.Page 7 of 37
Constellation
- Nuclear Services
- 61 Calculation No: NMPAST-02-001
'Rev. 2 Date:6December 22,2003 Table 5.3.1. Release/Intake Elevations Point of Interest Elevation Elevation Reference Unit 1 Main Stack 350 106.7, Pa e 11-35, Ref. 15.
-Unit 1 Reactor Building Blowout Panel"1.
78.9.
.24.0 Ref. 10 Unit 1 Turbine Building Blowout Panel
72.4 22.1............
.Ref 10 Unit 2 Main Stack 429ý 1.3038 Table 1, Ref. 16 Unit 2 Combined :Radwaste & Reactor 187 57 Section 11.3.3.1, Building Vent Ref. 19 Unit.2Main Steam Tunnel 2 45.08 13.7 Ref. 20 Unit 2 Standby Gas Treatment System 23.5 7.2 Ref. 21, Buildingrz2 Unit 2:Control Room Intake West-High 36 1
Ref. 22 Unit 2 Control Room Intake West-Low3 15.5 4.7 1 Ref. 22 Unit 2 Control Room Intake East, Highjjh M 52.75 16.1 j Ref.22.
Unit 2 Control Room Intake East-Low1'6 19 5-8 Ref. 22 Notesi
- 1. Elevation relative to bottom of blowout panel.
- 2. Elevation relative to bottom of louvered exhaust.
,3. Elevation relative to bottomn of intake. "
- 6. Assumptions
- 1. North-south :dimension of Unit I Turbine Building = 116'5" 35.48 meters (Ref. 23).
This assumption is taken to approximate the dimension of the. Unit 1 Turbine Building for the purposes of calculating the building wake area.
- 2. East-west dimension of Unit 1 Turbine Building= 2x(23' 6") + 14x20' =327'= 99.67 meters (Ref. 23). This assumption lis taken to approximate the dimension of the Unit 1I Turbine Building foreTthe purposes of :calculating the building wake area.
3;. Unit I Control Room intake height: above grade = 333' - 261' = 72'.- 21.95 meters.
(Ref. 24) Assumes the intake height is equal to roof elevation, This assumption is taken.to approxi mate the height of the intake as it is not apparent from the.references.
- 4. PASS Panel Vent release height above grade = 339' +4' (curb) - 261' = 82' =25
- meters. (Ref. 25) Assumed to include 4' high conicrete-curb surrounding the vent location. This assumption istaken to approximate the vent release height as it is not apparent from the references.
.Page 8 of 37
Calculation No: NMPAST-02-00I Constellation Rev. 2 Nuclear Services
'Date: December 22,2003
- 5. Unit.1 releases to Unit 1 Control room intake building wake area is consetvatively assumed to be equal to :one half of the east-west Unit 1 Turbine Generator Building cross-sectional area. This assumption is to account for the complexity of the dense building:cluster at the NMVP site for Which it,'is difficult to accurately characterize the building wake area., This assumption conservatively results in higher X/Q values.
- 6. Unit 1 releases to Unit 2 Control Room intakes buildingwake area is conservatively assumed to be equal to north-south cross sectional areapof the Unit,2 Turbine Building.
As the building wake area is difficult to accurately characterize, this assumed area is a best estimate. The actual cross sectional area from the release point to the receptor may be slightlylgreater than the value determined from this assumption. Therefore, this assumption conservatively results in higher X/Q values.
- 7. Unit 2 releases to Unit 1. Control Room intake and Unit I Technical Support Center, with the exception of the Unit 2 Main Stack release, building wake area is conservatively assumed to be equalto north-south cross-sectionaelarea of the 'Unit 2 Tur(bine Building.
As the building wake area is difficultto accurately characterize, this assumed area is a best estimate. The actual[ cross sectional area fromltherelease point to the receptor may be slightly greater than the value determined from this assumption. Therefore, this assumption conservatively resuIts; in higher X/Q values.
- 8. Unit 2 Standby Gas Treatment System Building and Unit 2 Main Stack releases to Unit, 2 Control Room intakes building wake area is conservatively assumed to be equal to the Unit 2 Reactor Building cross-sectional area. This assumption is taken since the Unit 2 Reactor Building is the dominant structure between the release point and the receptor location. This assumption is conservative because the actual building wake area may be larger due to neighboring structures.
- 9. Unit 2 Combined Radwaste & Reactor Building Vent and Main Steam Tunnel releases to Unit 2 Control room intakes building wake area is assumed to be 0.01 m2 (Ref. 5)for a zero wake term. This assumption is made because the Combined Radwaste &
Reactor Building Ventland Main Steam Tunnel release points are in close proximity to the, intakes. In this configuration it is difficult to characterize the building wake area and assure a conservative X/Q estimate. A zero wake term assumption conservatively results in higher X/Q values.
- 10. Unit 2 PASS Panel Vent release to Unit 2 Control room intakes building wake area.is conservatively assumed to be equal t0 one half of the Unit 2 Reactor Building cross-sectional area. This assumption.is to account for the complexity of the dense building cluster at the NMP site for which it is difficult to accurately characterize the building wakeiarea. This assumption conservatively results in higher X/Q values.
- 11. Unit 2 Main Stack-release is assumed to be a ground-level release as opposed to a stackrelease in ARCON96, This assumption is made because the NMP stacks are generally located in close proximity to the site building cluster.. The height of the stacks Page9 of 37
Constilatin 44Calculation No: NMPA$T-024.01 Rev.2 Nuclear Se, ces Date: December 22,,2003 are close to or below 2.5 times the height-of the site building structures. Also, regulatory guidance documents (Ref. 5) indicate that prope'rqualification of stack configurations must be made in orderto assume a stack release. Therefore, to alleviate the regulatory risk and to assure conservativeX/,Q estimates, this assumption has been made. The X/Q results from this assumption Will be. conservatively higher than those calculated as stack release.
- 12. Unit 1 Turbine Building Blowout panel release to Unit 1 Technical Support Center
.building wake area is conservatively assumed to be equal to the north-south Unit 1 Turbine Building Generator Building cross-sectional area. As the building wake area is:
difficult to accurately characterize, this assumed area is a best estimate. The actual cross sectional areafrom the, release point to the receptor may be slightly greater than the value determined from this assumption. Therefore, this assumption conservatively results in higher X/Q values.
- 13. Unit I Main Stack and Reactor Building Blowout Panel releases to Unit I Technical:
Support Center-building wake area is assumed to be 0.01 m2 (Ref. 5) for a zero wake term. This assumption is made because the release points are in: close proximity to the intakes. In this configuration itis difficult to characterize the building wake area. A zero wake term assumption conservatively resultsjin higher X/Q values.
- 14. Elevation change from the mid-point of the Unit 1 Turbine Building Blowout Panel to Unit I Technical SupportCenter is 62' or 18.9 meter (Ref. 18)1. The-elevation of the mid-point of the Unit 1 Turbine Building Blowout Panel is approximately (354' + 334') 12
-261'
= 83" according to Reference 10.
Therefore, the elevation of the Unit 1 Technical Support Center is assumed to be 83 - 62' = 21' = 6.4 m. This assumption is taken in lieu of a clear reference showing the height of the Unit 1 Technical Support Center intake structure.
7.,Calculations and Results
.7.1'. Releaselintake Distances and Directions Calculations Table 5.2.1 list the distances and-directions provided in the X/Q calculations performed
'previously by MES. These MES calculations fail to provide the distances and sector bearings for the following releases to the Unit 2 Control Room intakes: (1) Unit 1 Reactor Building blowout panel, (2) Unit I Turbine Building blowout panel, (3) Unit22Main Steam Tunnel, (4)
Unit 2 Combined Radwaste & Reactor Building Vent, (5) Unit 2 PASS Panel vent and (6) Unit 2 Standby Gas Treatment Building vent. Furthermore, the MES calculations also fail to disclose the distances and bearings for the Unit 2 releases to the Unit 1 Technical Support Center. The data listed in Table 5.2.1 was used to calculate the distances and directions for the above releaselintake combinations by developing a coordinate system. The Unit 2 Main Stack: release point was defined as the origin. :Figure 7.1.1 shows a schematic depicting the coordinate system used. The.coordinate axes, x and y, were respectively aligned with'the "true north" and "true east."
Page 10 of 37
C_
Cal~culation No: NMpAST-02-OO1 Comsell~onRev.
2 Nuclear ervlces Date: December 22,2003 The calculationswere performed using standard geometry:and a Microsoft@ Excel spreadsheet.. The unknown distances and directions were calculated in,four basic steps: (1) coordinates of the Unit 1. Control Room intakewere calculated, :(2) the Unit 1 Control:Room intake coordinates. were used to calculate the coordinates of the six release points listed above and also the Unit I Main Stack, (3):the Unit 1 Main Stack coordinates were used to calculate, the Unit: 2 Control Room.:intake coordinates.and (4) the coordinates of the Unit 2 Control Room intakes and the six releases points listed above were used to calculate the distances and directions. A procedure analogous to the above was Used to calculatethe distances and directions to the Unit 1 Technical SupportCenter for the following Unit 2 releases; (1).Main Steam Tunnel, (2):Combined Radwaste & Reactor Building Vent, (3) PASS Panel and (4)
Standby Gas Treatment System Building. The simple geometry formulations listed below were implemented:
&Ax d, sin(O),
Ay= d.cos(9) and a = tan-'I I
.=.a + SW Ay) where, Ax is the change in the x coordinate, AY is the change in the y coordinate, 0 is the angle relative to "true north," cc is the angle relative to the negative y-axis (1t80 degree or south) and d is the distance between two points. Table 7.1.1 shows thecoordinates calculatedfor the.
various release/intake locations previously listed. Table 7.1.2 shows. the calculated distances and directions-for various releases to the Unit 2 Control Room intakes. Table 7.1.3,shows the calculated distances and directions for various releases to the Unit 1 Technical Support Center.
Page 11 of 37
r7
- 4Conste.la"on Nuclear Slervices Calculation No: NMPAST-02.;001 Rev. 2 Date: December 22, 2003 True North, Plar ltNorth
,, N A
ynW2 y Main Stack x
Figure 7.1.1. Schematic of Coordinate Usedin Cailculating Releaselintake Distances and Directions
.Page12 of '37
Caonstllation Nuclear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Table 7.1.1. Summary Table of Calculated Coordinates of Release/Intake Locations for Units I and 2 Coordinates FROM:
"ITO
'TAx.(ft)
Ay ft) d(ft),d (min),,(deg)j x(ft) y (ft) I Location Unit 2 Main Stack,
.Unit 1 Control Room Intake
-108215 815.46113551 4313 2331-71082.5 -8 15.46 Unit i Control Room Intake Unit
- Rx Bldg. Blowout Pane Unit I Control Room Intake 175.1 -291.44 340 103.6 149 -1257.26 -524.02 Unit I Rx Bldg. Blowout Panel Unit 1 Turbine Bldg. Blowout Panel 210.28 -107.14 236 71.9 117 -1292.43 -708.32 Unit 1 Turbine Bldg. Blowout Panel Unit 2 Main Steam Tunnel
-543.56 -.242.01 595 181 246 -538.59 -573.45 Unit 2 Main Steam. Tunnel.
Unit 2 Combined RxiRwVent
-561.83 -250.14 615 187 246 -520.32 -565.32 Unit 2 Combined Rx/RwVent, Unit 2 PASS
-505.591 -424.24 660 201 230
-576.56 -391.22 Unit 2 PASS Unit 2 Standby Gas
-706.36 -375.58 800 -244 2421 -375.79.-439.88 Unit 2 Standby Gas.
Unit 1 Main Stack.
Unit 1 Control Room Intake 96.77 -388.12 400 121,9 166 -1178.92 -427.34 Unit 1 Main Stack Unit t Main Stack.
Unit I Technical.Suppor Center,,
212.12 -252.79 330 100.6 140 -.96.6.80 -680.14 Unit 1 Technical Support Center Unit 1 Main Stack Unit 2 Control Room - West High 630.95 ý386.65 740 225.6 121.5.-547.97 -813.99 unit 2 Control Room-West High.
Unit 2 Control Room - West Low 626.66.'-354.54 7201219.5 119.5 -552.26 -7861.9 Unit 2 Control Room - West Low Unit 2 Control Room,- East.High 725.05 *-338.09 8001243.8 115
-453.87,-765.44 Unit 2 Control Room - East High Unit.2 Control Room - East Low 725.05 -:338,09 8001243,81 115 -453.87 -765.44 Unit 2 Control Room-East Low Page 13 of 37
Constelladton Nuclear Services Calculation No: NMPAST,02,001 Rev. 2 Date: December 22, 2003 Table 7.1.2. Summary Table of Distances and Directions forVarious Releases to Unit 2 COntrol Ro0m Intakes FROM ITO A(ft) IAy (ft) d (ft) 1.d (ii, 0 (deg Unit 1 Rx Bldg. Blowout Panel.
Unit'2 Control Room..- West High, 709.30 -289.97'76628 233.56 112.24 Unit: 2 Control Room _.West Low 705.00 -257.86 750.68 228.81 110.09 Unit 2 Control Room - East High 803.39 -241.41 838,88 255.69 106.73 Unit 2 Control Room - East:Low 803.39 -241:41 838.88 255.69 106.73 Unit 1 Turbine Bldg. Blowout Panel.
Unit 2 Control Room - West High 744.46 -105.67 751.92 229.19 98.:08 Unit 2 Control Room.-. West Low
-740--.16,
-7357 8743.1 226.71 95.68 Unit,2 Control Room - East High 838.56
-57.12.840.50 25618 93.90 Unit 2 Control Room - East Low 838.56
-57.12 840.50 256.18 93.90 Unit 2 Main Steam Tunnel Unit 2 Control Room - West High
-9.37 -240.541240.72 73,37 182.23 Unit 2 Control Room -West Low
-13.67 -208.43 208.88 63.67 183.75 Unit 2 Control Room - East High, 84.72 -191.98.209.85 63.96 1'56.19
.Unit2 Control Room - East Low 84.72 -191.98 209.85 63.96 156.19 Unit 2 Combined Rx/Rw Vent Unit 2 Control Room - West High
-27.65 -248.67 25021 76.26 186.34 Unit 2 Control Room - West Low
-31.94 -216.57 2189.91 66.72 :188.39 Unit.2 Control Roorri-East High 66.45 -200.12 210.86 64.27 161.63 U unit, 2 Control Room East Low 66;45 ;-200.112 210.86 64.27 618.63 Unit 2 PASS Unit2 Control Room-West High 28.60 -422.77 423.74 129.15 17.6.13 Unit 2 Control Room -West Low, 24.30 -390.67 391.42.119.31 176.44 Unit2 Control Room-East High 122.69 -374.22 393.81 120,03 1161.85 Unit.2 Control Room -East Low, 122,69 -374.22 393.81 12003 161.85 Unit 2 Standby Gas Unit 2 Control Room - West High
-172.17 -374.11 41 !83 125.52,204.71 Unit 2 Control Room - West Low
-1 76.47 -342,00q 384.85 117.30 207.29 Unit 2 Control Room-East High
-78.08 -325I55 334.79 102.04 19,3.#9 Unit 2 Control Room - East Low
-78,08-325.55 334.79 102 04 193149
- Z-W, I3 a'
-J Page 14 of 37
Calculation'No: NMPAST-02-001 Consteeuatuiph Rev. 2 Nuclear Services Date: December 22, 2003 Table 7.1.3. SummaryTable of Distances and Directions of Unit 2 Releases to the Unit I Technical Support Center FROM ITO A.(ft)
Ay'(ft)I d(ft) d(m) I0(deg)
Unit 2 Main Steam Tunnel Unit E Technical Supiport Center
-42821 -10.68 444130 134.51 256.01 Unit2.Combined RxIRwVent Unit 1 Technical Support Center 446148 -11482 461.01 140.51 255,58 Unit 2 PASS Unit :1 Technical Support Center
-390,24 -288.92 485,55 148'00 233;49 Unit 2 Standby Gas Unit 1 Technical Support Center
-591.01 -240.25 0637.97 194.45 247.88 P4 Pg15of 37
ConlstellBation*
Calculation No: NMPAST-02.O401
~onsea~aIouuRev.12 Nuclear Services Date: December 22, 2003 7.2. Building Wake Areas Dueto the complexity of the geometry of the-structural buildings for both Units i and 2, conservative building wake-areas were calculated. Theconservative assumptions taken to calculate the wake areas:are stated in 5 through 10, 1,2 and 13,of Section.6.1. The calculations for determining building wake areas are as follows:
Unit I Releases to Uni't I Control Room Intake Per assumption 5 of Section 6.1, the contributing building area is conservatively assumed to be one half of the east-west cross-sectional area of the Unit 1 Turbine Generator Building.
Effective Height of Unit 1 Turbine Generator Building "Height of Generator Building - Height of Unit 1 Control Room Intake = 33 m -21.95 m = 11 m.
One half east-west length of Unit 1 Turbine Generator Building= 0.5xx I99.67m = 49.8m Wake Area for All Unit 1 Releases to Unit I Control Room Intake = 11 m x 49.8 m = 550 m2 Unit I Releases to Unit 2 ControlRoom Intakes Per assumption-6 of Section 6.1, the contributing building area is conservatively assumed to be the north-south cross-sectional area of the Unit 2 Turbine Building. The height of the intakes is assumed to be the maximum of all four Control Room intakes.
Effective height of Unit 2 Turbine Building = Height of Turbine Building - MaxxHeight of Control Room Intakes,= 36.58 m - 16.1 m = 20.4 m North-south length of Unit 2 Turbine Building =42.67 m Wake Area for All Unit 1 Releases to Unit 2 ControlRoom Intakes = 20.4 m x 42.67 m =
870 m2 Unit 2 Releases to.Unit 1 Control Room Intakes (ExcludingU nit 2Main Stack Release)
Per assumption 7 of Section 6.1, the contributing building area is conservatively assumed to be the north-south cross-sectional area-of the Unit 2 Turbine Building.
Effective ýheight of Unit2 Turbine: Building =,Height of Turbine Building -,Height ofUnit 1 Control Room Intake =36.58 m-21.95 m = 14.6 m North-south'length of Unit 2 Turbine Building = 42.67.m Page 16 of 37
Calculation No, NMPAST-02-O01 Rev. 2 Nuclear Services Date: December 22,2003 Wake Area for All Unit 2 Releases-(Excluding Unit"2 Main Stack) to Unit 1 Control Room Intakes = 14.6 m x 42.67 m = 623m2 Unit 2 Releases to Unit 1 Technical Support Center (Excluding Unit 2 Main Stack Release)
Per assumption 7.ofSection 6. 1,the contributing building area is conservatively assumed to "be the north-south cross-sectional area..of the -Unit 2 Turbine Building.,
Effective height of Unit 2 Turbine Building = Height of Turbine Building -:Height of Unit 1 Technical.Support Center = 36.58:m -6.4 m,= 30.18 m North-south length of Unit 2 Turbine Building = 42,67 m
'Wake Area for All Unit 2 Releases (Excludinq Unit 2 Main.Stack) to Unit I Technical Support
.Center = 30.18 m x 42.67.m-= 1287 m 2 Unit2 Main Stack Release to Unit I Control Room Intake The Unit 2 Main Stack displacement from the Unit 2 Reactor and Turbine building is sufficient such that the building wake area for-the Unit.2:Main Stack to the Unit 1 Control Room intake includes both'the entire area of the Unit 2 Reactor Building and.the north-south cross-sectional area of the. Unit 2 Turbine Building.
'Effectiveheight of Unit 2 Turbine Building = Height of Turbine Building -Height of Unit 1 Control Room intake = 36.58m -
21.95 m, 14.6 m.
Effective height of Unit2.Reactor Building = Height of Reactor Building - Height of Unit 1
'Control Room Intake = 51.55 m - 21.95 m = 29.6 m North-south length of'Unit 2 Turbine Building = 42.67 m Diameterof Unit 2 Reactor Building = 2 x 26.06 rm = 52.1 m Wake Area of Unit,27Turbine Building.= 14.6 m x:42.67 m = 623 m 2 Wake Area of Unit 2 Reactor Building = 29.6 m x 52.1 m = 1r542 m2 Wake Area for Unit 2 Main Stack Release to Unit 1 'Control Room Intake = 623 m2 + 1542 m2 =
2165 m2 Unit 2 Main Stack Release to Unit 1 Technical Support Center The Unit 2 Main Stack displacement from the, Unit,2 Reactor and Turbine building is sufficient such that the building wake area for the Unit 2 Main Stack to the Unit. Technical Support Page 17 of 37
Fa
-Calculation No: NMPAST-02-001 Rev 2Z Date:,December,22, 2003 Center includes both the entire area of the Unit 2 Reactor Building and the north-south cross-sectional area of the Unit 2 Turbine Building.
Effectiveiheight of Unit.2:Turbine Building = Height of Turbine Building - Height of Unit I Technical Support Center = 36.58 m -6.4 m =30.18 m Effective height of Unit 2 Reactor Building = Height of Reactor Building - Height of' Unit 1 Technical Support Center = 51.55-m -6.4m = 45.15 m
.North-south.length of Unit 2 Turbine Building = 42.067 m Diameter of Unit 2 Reactor Building = 2 x 26.06m = 52.12 m Wake Area of Unit 2 Turbine Building = 30.18 m x42.67 m = 1287 m2 Wake Area of Unit 2 Reactor Building = 45.15 m x 52.12 m = 2353 in2 Wake Area for Unit 2 Main Stack Release to Unit I Control Room Intake = 1287 m2 + 2353 m2
=3639 'm 2 Unit 2 Standby Gas System Building and Unit 2 Main Stack Releases to Unit 2 Control
.Room Intakes Per assumptions 8-of Section 6.1, the contributing building area is conservatively assumed to be the cross-sectional area of. the Unit 2 Reactor Building. The height of the intakes. is oassumed to be the-maximum of all four Control Room intakes.
Effective-height of Unit 2 Reactor Building = Height of Turbine Building - MaxkHeight of Control
'Room Intakes = 51.55 m -16.1 m = 35.4m Diameter of Unit 2 Reactor Building =2 x 26.06 m = 52.1 m Wake Area for Unit 2 Standby Gas SSystem Building and Unit 2 Main Stack Releases to Unit:2 Control Room Intakes = 35.4 m x 52.1 m =1844 m2 Unit 2PASS Pane Vent Release to Unit2 Control Room Intakes Per assumption 10 of Section,61, the contributing building area is conservatively assumed to be one half the cross-sectional area of the Unit 2 Reactor Building. The height of the intakes iS assumed to' be the maximum of all four Control Room intakes.
Effective height of Unit 2 Reactor Building = Heighttof Reactor Building - Max Height of Control Room Intakes =-51.55 m -16.1 m =35.4 m Diameter of Unit 2 Reactor Building =_2 x 26-06 m = 52.1 m Page 18 of 37
Constellati o Nuclear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Wake Area for Unit2 PASS.Panel Vent Releaseto Unit2 Control Room Intakes:.= 0.5x 35.4 m2 x52.1 m =-922 m2 Unit I Turbine Building Blowout Panel Release to Unit I Technical Support Center Per assumption 12 of Section 6.1, the contributing building area is conservatively assumed to be the north-south cross-sectional area of the Unit 1 Turbine Building.
Effective Height of Unit I Turbine Generator Build ing := Height of Turbine Building - Height of Unit 1 Technical Support Center = 33m-6.4 m = 26 m.
North-south Length of the Unit l Turbine Building =35.48 m Wake Arealfor Unit I Turbine Building Blowout Panel Release to Unit I Technical Support Center = 26.6 m x 35.48 m = 943 m2 Table 7.2.1 summarizes the building wake areas calculated above.
Table 7.2.1. Calculated Building Wake Areas
- Release Intake Area (mi)
,Unit 1.-All Unit 1CR 550 Unit I
- Main Stack Unit I TSC
,0.01 !
,Unit I - Reactor Building Blowout Panel....................
Unit 1 -Turbine Building Blowout Panel Unit 1 TSC 943 Unit 1 -All Unit2 CR-All: 870 Unit2-All Except Main Stack Unit 1 CR 623 Unit 2 - All, Except Main Stack Unit 1. TSC 1287 Unit 2 - Main Stack Unit 1 CR 2165:
Unit.2 - Main -Stack Unit 1 TSC 3639 Unit.2-Standby Gas Building Unit2 CR-AII
- 1844, Unit2 - Main Stack Unit2 -PASS Panel Vent I Unit 2 CR -All,.
922 Unit2 - Combined Radwaste/Reactor Building Vent Unit 2 CR -Al 0.01 1 Unit2 - Main Steam Tunnel I**,I:in accordance with assumptions 9 and 13 of section 6.1.
Page 19 of 37
CalculationNo: NMPAST-02-001 Rev.:2 NudearServices Date: December 22,2003
- 73. X/Q Values The ARCON96 input is comprised of release/intake specific data and some default input parameters, The ARCON96 user's guide (Ref. 2:).provides the details of the default input data.
All releases have been treated as ground-level releases, including both stack: releases.
Regulatory guidance (Ref. 5) suggests the use of stack release mode in ARCON96 when the
,release. point is greaterthan 2.5.times the height of adjacent build ings. Following this specification the Unit 1 stack release is clearly considered a ground-level release. The Unit.2 Main Stack is only slightly greater then 2.5 times the Unit.2 Reactor Building. Since,this guidance (Ref. 5) suggests that ARCON96 can calculate non-conservative X/Q values in stack release-mode and given the consideration that the Unit 2. Main Stack is very close to 2.5 times the Unit 2 Reactor'Building.height, the mode of release provided in the ARCON96 for all Unit'2 Stack releases is ground-level. This is consistent with assumption 11 above inSection 6.
The diffuse area:source as described in the regulatory guidance (Ref. 5)-was also considered for the Unit I Turbine Building and Reactor Building blowout panel release scenarios.
ARCON96 runs were: performed using the diffuse area:source input for ARCONg6 (as describedin Ref. 5). The results suggest thatthe values calculated with the diffuse-area source are slightly less conservative than the values calculated by considering the blowout
'panels as a finite :point. Therefore, :no diffuse area sources have been implemented in the ARCON96 runs.
ARCON96 requires the direction data fordeach release/receptorto be'input asthe direction ffrom the intake to the release. To this point, the directions listed above in Tables 5*2.1 and 7.1.2 were inverted by 180 degrees. The final distances and directions..are provided in Table 7.3.1.
The input common to all runs.is comprised mainly of default data. The: regulatory guidance (Ref. 5) also provides guidance on values of default input data. The values specified in the regulatory guidance (Ref. 5) were usedinstead of those provided in the ARCON96 user's manual (Ref. 2). Table 7.3.2 lists.the ARCON96 common or default input that was used and the reference for that input data.
A representative input file is included in Appendix A. Due to the number of computer runs perforrned the'input and output files have been, provided on the enclosed CD. Appendix C provides a list of computer runs and Appendix D provides a listing of:all files on the enclosed CD.
Table 7.3.3-1 providestabular results of the.X/Q values for all releases to the Unit I,Control Room ýand Table,7.3.3-2 provides results of the :X/Q values for all releases to the Unit 1 Technical Support Center. Table 7.3.4 provides tabular results ofthe X/Q values for all releases to the Unit 2 Control Room.
The results presented in Tables 7.3.3-1 through 7.3.4 are based on revised meteorological data (Refs. 27 and 28.).
Page 20 of 37
Consteflationc Nuclear ServiceS Calculation: No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Table 7.3.1 ARCON96 Distances and Directions Inputt FROM TO Distance Direction
_.............._(M
)
(degrees)
Unit I Control Room Intake
'Unit 1 Reactor Building Blowout Panel 103.6 329 Unit I Turbine Building Blowout-Panel 71.9 297 Unit. : Main Stack 121.9 346:
Unit 2:Combined Radwaste & Reactor 187 66 Building Vent' Unit 2 Main Steam Tunnel 181 66
.,Unit 2 Standby Gas Treatment System 244 62
.B uilding...
Unit 2.Post Accident Sampling System 201 50
- Panel
..Unit:2 Main Stack 413 53 Unit 1 Technical Support Center Unit 1 Reactor Building Blowout,,Panel 104.5 266 Unit 1 Turbine. Building Blowout'Panel 1 100,0 266 Unit I Main Stack.
100.6:
320 Unit 2 Combined Radwaste & Reactor 140.51 75.58 Building Vent Unit 2 Main:Steam Tunnel 134,51 76.0-1 Unit 2 Standby GasTreatment Systerm 1,94.45 67.688 Building_
Unit 2 Post Accident Sampling System 148.00 53.49 Panel Unit 2 Main Stack 360.29 54;87 Unit 2 Control Room Intake West - High Unit I Reactor Building Blowout Panel 233.56 292.24
- Unit 2 Control Room Intake West - Low.
228&81 290.09 Unit 2 Control Room Intake East - High 255.69, 286.73,
.Unit 2 Control Room Intake East - Low.
255.69 286.73 Unit 2 Control Room Intake West L: High Unit 1 Turbine Building Blowout"Panel 229.19 278.08
,-Unit 2 Control Room Intake West - Low 226.71 275.68 Unit 2 Control Room Intake East - High 256.18 273,90 Unit 2 Control Room Intake East-Low.
256.18 273.90 Unit 2 Control Room Intake West - High Unit I Main Stack, 225.6 301.5.
Unit 2:Control Room Intake West-Low 219.5 299.5 Unit ;2Control Room Intake East - High 2438.8 295 Unit 2 Control Room Intake East - Low 243.8 295 Unit 2 Control Room Intake West -, High Unit 2 Combined Radwaste & Reactorf 76.26 6.34 Unit 2 Control Room Intake West - Low Building Vent 66172 8.39 Unit 2 Control:Room Intake East -,High
- 64.27 341.63 Unit 2:Control: Room Intake East - Low 64.27 341.63 Unit 2 Control Room Intake West -High Unit 2 Main Steam Tunnel 73.37 2.23.
Unit 2 Control Room Intake West - Low 63.67 3.75 Unit 2 Control Room Intake East - High 63.96 336.19 Unit 2 Control Room Intake East - Low 63.96 336.19
.Unit 2 Control Room Intake West - High
- Unit 2 Standby Gas Treatment:System 125.52 24.71 UnitW2 Control Room Intake West - Low Building 117.30 27.29 Page 21 of 37
Constellation Nuclear Services Calculation No: NMPAST-02-001 Rev.2 Date: :December 22, 2003 FROM TO Distance Direction (m)
(degrees)
Unit 2 Control Room lntake East'- High 102.04 13.49 Unit2 Control Room Intake East - Low 102.04 13.49 Unit 2Control Room Intake West - High Unit 2'Post Accident Sampling System 129.15 356.13 Unit-2 Control Room Intake West - Low
- Panel, 119.31 356.44
- Unit 2 Control Room Intake East -High 120.03 341.85 Unit 2.Control Roomn Intake East.-.Low 120.03 341.85 Unit 2 Control RoomIntake West - High Unit 2'Main Stack 286....
45 Unit 2 Control Room Intake West - Low 280 45
- Unit 2 Control Room Intake Eastý-.High 257 22.5 Unit2"Control Room Intake East-Low 1258 22.5 Table 7,3.2. List of Common/Defaulttinput Data to ARCON96 Input Parameter Value Used Reference.
Lower Wind Measurement 9.45.m Ref. 8 Height UpperWind Measurement 60.66 m Ref. 8
-Height Wind Speed Units 2 (mph)
Ref. 26 Release Type.
1I (ground release)"
Assumption 11 Stack Velocity.
0
,Assumption 11 Stack Flow 0
Assurmption 11 Stack Radius 0
Assumption 11 Elevation Difference 0
Ref. 5 Surface Roughness, 0.2 m Ref. 5 WindDirection Window 90 degrees Code Default Minimum Wind Speed 0.5 rm/s Code Default Averaging Sector'Width 4.3 Ref. 5 constant Initial Diffusion Coefficients
- 0.
Code Default Hours: in Averages see user's guide (Ref. 2)
Code Default Minimum Number of.Hours see user's, guide (Ref. 2)
.QCode Default Expanded Output n
'Code Default Page 22 of 37
GO constelat Nudear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Table7.3.3-1. X/Q Values for the Unit 1 Control Room XJQ DispersionCoefficients (s/4 3)
Release Point 0-2 hrs 2-8 hrs 8.24 hrs 1-4 days 4-3 days U1 Reactor Bldg. Blowout Panel 4.82E-04 2.61E-04 9.25E-05 6.70E-05 4.93E-05 Ul Turbine Bidg. Blowout Panel 1-.03E-03 5.85E-04 2.07E-04 1.75E-04 1.52E-04 Ul Main Stack.
1227E-04 126E-04 4.30E-05, 3.58E-05 2.59E-05 U2 Combined Radwaste & Reactor'Vent 1.77E-04 i1.09E-04 3.92E-05 2.48E&05.1 85E-05 U2 Post Accident'Sampling Sys. Panel 1 P59E-04 1.13E-04 4.19E-05,2.48E-05 2.OOE-05 U2.Standby Gas Treatment Sys. Building 1.11E-04 8;09E-05 2.91iE-05 1.82E-05 1-45E-05 U2 Main Steam Tunnel I... 1 90E-04 1.37E-04 4.93E-05 3.1i2E-05 2.56E-06 U2 Main Stack I 4118E-051 2.30E.051 8.94E-06 5.62E-06 4-31E-06 Table 7.3.3-2. X/Q Values for the Unit I Technical Support Center X/QDispersion Coefficients (s:I M)3 Release Point, 0-2 hrs 2-8 hrs 8-24 hrs 1-4 days 4-30 days U 1 Reactor Bldg. Blowout Panel, 7.09E-04 5.60E-04 2.34E-04 1.71 E-04 1.41.E-04 UI Turbine Bldg. Blowout Panel 5.91 E-04 4.26E-04 1.63E-04 1.35E-04
- 1. 16E-04 UI MainStack 3147E-04 2.42E-04 8.22E-05 6.06E-05 5.00&E05 U2 Combined Radwaste & Reactor Vent 2.70E-04 1.64E.04 5.41 E-05 3.86E-05 2.86E-05 U2 Post Accident Sampling Sys. Panel 2-69E-04 1.91 E-04
- 7. 19E-05 4.22E-05 3.40E-05 U2 Standby Gas Treatment Sys. Building I.62E-04 1.19E-04 4.28E-05 2.72E-05 224E-05 U2 Main Steam Tunnel 3.27E-04 2.411E.04 8.38E-05 6595E-05 4.76E-0!5 U2,Main Stack, 4-95E.05 2.69E-65 1 03E&-05 6.67E-06 4.85E&06 Page 23 of 37
Con-stuelaion S Nuc lear Services!
Calculation No: NMPASTr02-001 Rev. 2 Date: December 22i 2003 Table 7.314. XIQ Values for the Unit,2 Control Room
.... _______U2 Control Room Intake - Upper, West U2 Control Room Intake, Upper East X/O Dispersion Coefficients s Im 3):
xQ Dispersion Coefficients (s.I m3)'
Release Point 0-2 h
-s 24 hrs 8-24 hrs 1-4 days 4-30 days*
0-2 hrs 24 hrs 8-24 hrs 1-4d A-0days U1 FOeactor Bldg. Blowoui Panel
.1,23E-04 7.21E-05 2.57E-05 2.28E-05 2.05E-05 1-06E-04 6.70E-051 2.39E-05 2.17&-05 1.96E-05 Ul lturbineBldg. Blowout Panel 1.30E-04 9.03E-05 3A.5E-05I 2.92E-05 2.56E-05 1.09E-04 7173E-05 2.95E-05 2.45E-05 2.14E-05 Ul iain Stack 1.061204 5.90E-05 2,23E-05 I 73E-05 1.43E.05 9.83E-05 5.81 E-05 2.22E-05 1.83E.05 1,57E-05 U2 Combined Radwaste & Reactor Vent 8.24E-04 6.29E704 2.28E-04 1.56E-04 1.26E-04 1.09E-03 7.23E'04 2.46E-04 1.92E-04 1.47E,04 U2 Post Accident Sampling Sys. Panel 3,36E-04 2.00E-04 7.31E-05: 5.53E-05 4.04E-05 3.74E-04 2.05E-04 7.08E-05 5.412-05 3.88E-05 U2 Standby Gas Treatment Sy n
362E-04 2.59&-04 9.48E-05 6,16E-05 4.42E-05 5.31 E-04 370E-041 1.35E-04 9.16E-05 6.70E-05 U2 Main Steam Tunnel.
113E-03" 7.49E-04 2.76E-04 1.90E-04 1AGE-04 I 1.47E.03 8.80E-04 3.32E-04 2.26E-04 1.68E-04 U2 Main Stack 7.04E-05 3,95E-05. 1.49E-05 9.96E.06 7.46E-06 8.03Ew05 4A8E-05". 1.68E-05 1,20E-05. 8.83-06 U2 Control Room Intake -,Lower West U2 Control Room Intake - Lower East
-3 X/J Dispersion Coefficients (S,m),
XJQ e) I l son Coefficients (s IMi)
Release Point 0-2 hrs 2-8 hrs 8.24 hrs 1-4days 4-30 days
)0-2 hrs.., 2-rs h 8-24hy 43 days Ut Reactor Bldg. Blowout Panel 1.26E-04 7,73E-05 2.74*-05 2.45E-05 2.23E-05 I1M06E04 6.68E-05 2.39E-05 2.16E&05 1.95E-05 Ut Turbine Bldg. Blowout Panel 1.31E-04 9.42E;05 3.59E-05 3.01 E-05 2,63E-05 1.08E-04 7.698-05 2.96E-05 2.44E-05 2.14Et05 UI Main Stack J.1*E0E&4 6.16E-05 2.31E-05 1.85E-05 1.54E-05 9.54&-05 5.68E-05 2.152-05 1.79E-05 1.54E-05 U2 Combined Radwaste & ReactorVent 9.03E-04 6.93E-04 2.50E-04 1.71E-04 1.36E-04
.43E-04 6.34E-04 2.153E-04 iA67E-04 1.29E-04 U2 Post Accident Sampling ýSys. Panel 3.84E-04 2.28E-04.8.23E-056....6ý28E-05 4 57E 05 3.67E-04 2.01 E-04 6.952-05, 5.32E-05 3.83E&05 U2 Standby Gas Treatment Sys, Building
4.0 5E-04
2.95E-04 1.08E-04 6.98E-05.5.00E-05 5.33E-04 3.72E-04 1.36E&04 9.17E-05 6072E405 U2 Main Steam Tunnel 1,.46E-031 9.74E-04 3.63E-04 2 45E-04 1.90E-04 i.. 46E-031 8.70E-04 3.32E-04 2.23E-041 1.68E-04 U2 Main Stack
-4 Page 24 of 37
Calculation No: NMPAST-02-001 Rev. 2 Nuclear Services Date: December 22,2003 8.
Conclusions:
Atmospheric dispersion coefficients (X/Q) values have been calculated at the conitrol room intakes at both :Units 1 and 2 and the Unit 1 Technical.Support Centerdue to all postulated release scenarios. Tables 7.3.3-1., 7.3.3-2 and 7.3.4 provide conservative X/Q-values for the
,scenarios listed above.
- 9. References
- 1. NMP Purchase Order, No. 02-40502, May,22, 2002.
- 2. NUREG/CR-6331, "Atmospheric Relative Concentrations in Building Wakes," May 1997.
- 3. Regulatory Guide 1.145, Rev. 1, "Atmospheric Dispersion Models for Potential Accident
- Consequence Assessmrents at Nuclear Power Plants,",February 1983.
- 4. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluation Design BasisAccidents at Nuclear Power Reactors,"July 2000.
- 5. Draft.Regulatory Guide DG-1111 and RegulatorY Guide 1.194, "Atmospheric. Relative Concentrationsfor Control Room Radiological Habitability Assessments at Nuclear Power Plants," U.S. NRC Office of Nuclear Regulatory, Research, December 2001 and June 2003.
- 6. CNS ARCON96 Computer Code Verification, Rev. 1, June 24, 2002.
- 7. CNS Quality AssuranceProgram, Rev. 4, December 1, 2002.
,Data".'
- 9. E-mail Ltr. from Thomas Galletta (NMP) to Shane Gardner (CNS), 4/24/2002, "NMP ARCON96 Met Data - No Tabs'.
- 10. NMP Unit 1 'Drawing, C-i 8713-C, Sht. 2, Rev. 9. 5/22174.
11...NMP"Unit 2 Drawing, EA-1A-7, Rev. 7, 5/31/83.
- 12. NMP Unit,2 Drawing, EA-3A-4, Rev. 4, 5/4/88.
- 14. NMP:.Unit 2 bUSAR Figure 1.2-11, Sht., Rev. 0, April 1989.
- 16. MES Calculation, 12/85, "Technical Support Document, Nine Mile Point Unit, 2, Accident and Long-Term Diffusion Estimates and the Methodology Used in their Calculation."
- 17. MES Calculation, 4/6/89, "X/Q. Values at the NMP Unit 1 Control Room Air Intake and Emergency Operations Facility for All NMP Unit 2 Release-Building Scenarios."
- 18. MES Calculation,Z8/7/90, "Accident.X/Q Values for Nine.Mile Point Unit I Releases from the Main Stack and the Reactor Buildings."
- 20. NMP Unit 2 Drawing, EV-202E-2, Rev. 2,,3/23/84.
- 21. NMP Unit 2 Drawing, EA-56B-5, Rev. 5, 51/31/83.
- 22. NMP Unit 2 Drawing, EA-46D-5, Rev..5, 5/24/84.
- 23. NMP Unit 1 Drawing, C-1 5350-C, Rev 5,.2/29/68.
- 24. NMP Unit 1 Drawing, 0-18717-C, Rev 21, :6/19/01.
Page 25 of 37
SConstellation Calculation No: NMPAST-02-001 C Rev.2 Nuclear Services Date: December 22,2003
- 25. NMP Unit 2 Drawing, EA-41A-6, Rev. 6, 4/30/91.
- 27. E-mail Ltr. From Thomas Galletta (NMP) to Shane Gardner,:(CNS), 8/11/02, "ARCON96 Data -Rev. I".
- Releases at NMP Units 1 and 2', 7/31/02, Rev. 0.
29.,E-mail from Tom Galletta to Shane Gardner and James Heffner (
Subject:
5 year JFD's),
Attachment:
"NMP 60mJFD_1997-2001 for CNS", July 25,2002.
- 30. Regulatory Guide 1.23, "Onsite Meteorological Programs,""February, 1972.
Page 26 of 37
- -1; '44
- Constellation Nuclear, Services:
Calculation No: N MPAST-02-001 Rev. 2 Date: December 22,2003 Append ices:
Appendix A - Site Plan Showing Associated X/Q Directions Appendix.B - Representative ARCON96 Input File Appendix C -:List of Computer Runs Appendix D - List of Files On CDROM Page 27 of 37
Constellation
- g.
oMLI Nuclear Services Appendix A - Site PPlan Showing Associated XIQ Directions 8-1
ýCalculation No: NMPAST-02-001 Rev. 2 Date: December 22,2003 1)
N N:W N
(WSW~~
7sv'iz~
Page 28 of 37
4WzI
. Constellation NuclearServices 8Z.
Calculation No: NMPAST-02-001 Rev. 2 Date: December:22, 2003 Appendix B - Representative ARCON96:Input File The following is a copy of the ARCON96 input file for the Unit 1 Main Stack release to the Unit 1 Control Room intake. Additional input files are ;provided on the attached disk.
1 C:,:\\NMP. CRXQ\\NMP_.R1..MET 9.45 60..66 2
106. 7.0 550-.00 0o. 00 0*. 00 0..600 346 90
.121. 90 21.'95
.0.00o
.U1MS U1.log UIMS _U. CFD
..'2 1I 0.50 4.3'0 2
2 0-. 00O
.4 4
8
.12 18 11 0.00 24 22 96 16,8 3'60 720 87 152 324 648 n2 Page 29 of 37
4IC4716- ýO Constellation Nuclear Services Calculation No: NMPAST.02-001 Revi.2
.Date: December 22, 2003 Appendix C- :List of ComputerRuns The ARCON96 computer run identifier and corresponding release/intake scenario are summarized in the listfbelow. The computer run identifier, in conjunction with the appropriate d file extension, defines the input.and output files for each run. The ARCON96 input file extension is ",RS.F and the output file extensions are "log" and '.CFD." The input and output files are included in the attached disk..
Table C-1. List of Computer Runs computer Run Identifier Release 1Intake U2STG U2UW Unit 2 Standby Gas Treatment Unit 2 CR - Upper'West U2STG U2UE System Building Unit 2.C.R -Upper East U2STG U2LW Unit 2 CR -Lower West U2STG U2LE Unit 2 CR - Lower East E U2STG.UI Unit 1 CR 1 U2STG UITSC Unit 1 TSC f"U2PASSV U2UW Unit2 Post Accident SamplIng Unit 2 CR - Upper West U2PASSV U2UE System Panel Unit 2 CR - Upper East iU2PASSV U2LW Unit 2 CR -Lower West iU2PASSV U2LE Unit2 CR-Lower East
-U2PASSV Ul Unit.1 CR U2PASSV UITSC Unit 1 TSC U2MST ýUUW Unit 2 Main Steam Tunnel Unit 2 CR - Upper West U2MST'U2UE Unit 2 CR - Upper East U2MST U2LW Unit2 CR - Lower West U2MST U2LE Unit2 CR - Lower East U2MST Ul Unit 1 CR U2MSTUITSC Unit 1 TSC U2MS U2UW Unit 2'Main Stack Unit 2 CR - Upper West U2MS U2UE Unit 2CR - Upper East
- U2MS U2LW Unit 2 CR - Lower West U2MS U2LE Unit 2 CR - Lower East U2MS U1 Unit I,CR U2MS UITSC..
Unit A1 TSC U2CRRV U2UW Unit.2 Combined Radwaste-&
Unit 2 CR -. Upper West U2CRRV U2UE Reactor Building Vent Unit: 2 CR - Upper East U2CRRV U2LW Unit`2 CR -,Lower West.
.U2CRRV U2LE Unit 2 CR - Lower Eastf
- U2CRRV UI Unit 1 CR U2CRRV UlTSC Unit 1 TSC UlT U2UW Unit 1 Turbine Building Blowout Unit,2 CR - Upper West U1T U2UE Panel Unit:2 CR - Upper East U1T U2LW Unit 2 CR -Lower West 7UlT U2LE Unit.2CR-Lower East UIT, UI Unit'! CRI UIT U1TSC Unit 1.TSC
- UIR U2UW Unit 1.ReactorBuilding Blowout Unit 2 CR - Upper West 7U1R U2UE Panel Unit 2 CR.- Upper East' U1R U2LW Unit 2 CR - Lower West U1R U2LE Unit :2. CR -.Lower East Page 30 of 37
Constellation Nuclear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Computer'Run Identifier Release fintake U1R U1 Unit1 CR U1R U1TSC.
Unit 1 TSC.
UIMS U2UW Unit 1 Main.Stack Unit 2 CR -UpperWest UiMS U2UE Unit 2CR-Upper East U1MS U2LW Unit 2 CR - Lower West U1MS U2LE Unit 2 CR - LowerEast UIMS Ul unit CR
- U1MS U.1TSC Unit' 1 TSC Page,31 of 37
Constelation Nuclear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003 Appendix D - Listof Files 'On CDROM Note: This directory listing does not include the calculation document, cover page and:review checklist files..
Directory of D:..\\
12/22/2003
&12/22/2003 09/09./2002
.12/22/2003
'08/ý02/2002 12/22/2003 i1/18/2003 05:
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)
-6 File (S)
<DIR>
<DIR>
28.,672 Distances CalcuLations.xis
<DIR>
Inputs andOýutputs 1,621,488 NMP_Rl.MET 30,208 Results Summary (MET DATA Rev l).xls
<DIR>
SCOPING
.4,359,152 bytes.
Directory of D:\\:Inputs and:Outputs
,12/2.2/2003
'12/22/2003
.11/182003 11/182/2003
ý12/22/2003 03:15.PM
<DIR>
03:15 PM
<DIR>
<D'iR>
02:27 PM
<DIR>
08-:05 AM
<DIR>
'1 File,('s),
1,544 run_revision2..bat UN IT I
-UNITI-TSC UNIT2 1,544 bytes Directory of D:\\Inputs and Outputs\\UNITM 11/18ý/2003
.0s5/0,9/1 997 06/27/1997 05/09/1997 12/22/2003
- 01/11/1994
- 12/22/2003
- 07/:29/2002,
'12/22/2003 12/2ý2/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22 /20 03 02:27 02:.27 03:00 12:41
.03: 00 03:09 12,:00 03.:11 01:21.
01; 57 01.57 01:,57 b01:: 57 01.: 57 01.: 57 01: 57 01:057 PM PM PM PM PM:
<DIR>
<DIR>
14,620 ARCHELP.fTXT 3.80,928 ARCON96F.EXE 143,612 ARCONVB2.EXE
<DIR>
CFD.
393,942 DOSXMSF.EXE
<DIR>
log
'545 run allrelease_ulcr.,bat 401 UIMSUI.RC7 381, UVIRU.RSF 3801. U1TUU.RSF 387 U2CRRV UI..RSF 385 U2MST Ul,.RSF 383 U2MS_UI.RSF, 389 U2PASSV_UI.RSF 385 U2STG_U!,.RSF 936,7.39 bytea 13 File (s)
'Directory of D;\\Znputs and Outputo\\UIMIT1\\CFD 12/22/2003 12/22i/2003 12/22/2003 12/22/2003 12/2212003 12/22/2003 12/ 2 2/2003:
"12/22/2003 12/22/2003 12/22/2003 03.: 09
.03: 09
.DIR>
<DIR>
11,168 11,168 11,.168
- 11, 168 UIMS Ul.,CFD U1R_:UI..CFD:
.UlT U1.CFD U2CRRV U1.CFD U2MSTui.lCpD U2MSUI.CFD IU2 PASS'J_Ii
- CFD U2STG UI.CFD
.Page 32 of 37
Nuclear Services CalIcuiation. No: NMPAST-02-001 Rev. 2, Date: December 22, 2003 8 File(s) 89,344 bytes Directory ofD:\\Inputs and,utputs'\\tUxIT1\\*0g 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2003 12/22/2002 12-/22/2003 03II PM
<DIR>
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<DIR>
021-53 PM 02:53 PM 02!:53 PM 02:53 PM 02t53 PM 02:53 PM 02:63 PM 02:53 PM 8 *Vi~(g) 4,8A1 IJIMS
.11-.].g 4,838 UIRU1.0log 4,838 UA".;1.1log 4,838 U2CRRVUI.log 4,838 U2MST1 U1log 4,838 U2MStU1..log 4,838 U2.PASSV_U1.log 4,838 U2STG_ U,.log 38,-704 bytes Directory of D-:\\Inputs and Outputs\\UNITI-.TSC
- 71I1.8/2o003 1.1/18/2003 05/09/1997 06/27/1997
- 05/09/1997
.12/22/2003 01111/1994 12/22/2003 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 12/22/2003 09/09/2002 09/09/2002; 02:2.7 02:.27 03 :00 12:41 03:00 03: 11 12:00 03: 11 01:09 01:06 01:24 01:06 01:06 01: 06 08:09 01: 06 01: 06 PM PM PM PM PM PM AM PM PM
<DIR>
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14,620 ARCHELP.TXT 380,928 ARCON96F.EXE 143,612 ARCON-VB2.EXE
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<DIR>
log 617 run allrelease ultsc~bat 407 UIMS UITSC.RSF 387 UIR_.UTSC..RSF 387 U131TUITSC. RSF 393 U2CRRV UITSC.RSF 391 U2MST UITSC.RSF 389 U2MS UITSC.RSF 395 U2 PASSVUITSC.RSF 391 U2STG UITSC.RSF 936,:859 bytes 13 File(s)
Directory Of D:\\Inputs and Outputs\\UNITl-TSC\\CFD
.52/22/2003 12/22/2003ý 09/09/2002 09/09/,2002' 09/09/2002 09/09/2002 09/09/2002.
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01:09 PM 01:09 PM 01:09 PM 01:09 PM 01:091 PM 02:53 PM 01:09 PM 01:09 PM B8 File.(s) 11,168 UIMSUITSC;CFD 11,168 UIR_ ITSCTSC.CFD 11,168 UIT UITSC.CFD 11,168 U2CRRVUITSC.CFD 11,168 U2MSTUITSC.CFD i,168 U2MSUITSC.CFD 11,168 U2PASSV_U1TSC:,.CFD 11,168 U2STGUITSC.CFD' 89;344.:bytes Directory of D:\\Inputs and Outputs\\UNITl-TSC\\logq 12/22/2003 12/22/2003 09/09/2002 09/09/2002 09/09/2002 09/09/2002 69/09/2002 12/22/20 03 03:,11 03: 11 01:.09 01: 09 01:09 01:09 01:09
,PM
<DIR>
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4, I1MS UITSC. 7og 41,838 U1RJI.TSCTSC.log 4,838 UIRUItCTSC.log 41,838 U2CRRV UITSC.1log 4,838 U2MST UITSC.log 4,f838 IJ2MSU1TSC.1og Page 33 of 37
constelation Nuclear Services Calculation No: NMPAST-02-001 Rev.:2 Date': December 22, 2003 0,9/0,9/2002 09/0 9/:2002 01:.09 PM 01:09 PM 8 Fi.e(s) 4,83R U2PASVqV UITSC.log 38, y2STGe TSC..lo 38,704, bytes
- Directory of rY\\TnPits and :Outputs\\WNIT2 12/22/2003 12/22 /.r2003 os/,09/1997
ý06/27/1997 05/0 9/1997 12ý22/2003 0,1.1/:
1994 12/22/20013 072 29/
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,09/09/2002 09/o09/2002 09/09/-2002 0.9/0"9/2:002
.09/:09/2002 09/09/20012 09/09/2002 0 9*/10 2 0.02
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O5 12:'41 03:00 03:10 12:,00 03": 12 01:20 01: 06 01;:06 01: 06
.01: 06 01:06 01I: 06 01:, 06 01:106 01: 06 01.: 06 01: 06 01.: 06 01: 06 01:.06 01::06 01.: 06 01 :06 01:,06 01:06 01: 06 08;,09 08: 09 08: 09 08: 09 08:: 09 08 :-09 08;-09 08::09 081:09 08:-09 08:0;9 08:'09 AM
- PM PM,
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.PM PM PM AM AM, AM AM AM AM AM AM AM.
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.14,.620 ARCHELP.TXT 380,928 ARCON96F.EXE
- 43,612 ARCONVE2.EXE
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<DIR>
log; 2,128 run',allreleaseU2cr.bat 387 UIMSU2LE.RSFý 387 UIMS_TU2LW.RSF 387 UIMSU2UE..RSF 3........
...1U2UW.RSPF 385 UDR _U2LE.RSF
-385. uiR uD2LW.RSF 385 UIRu2*E.RSF 3ý85 UIR U2UW..RSF 385 UITDU2LE.RSF
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.391 U2CRRVDU2LE..RSF 391 U2CRRVU2LW.RSF 391 U2CRRVD2U:..RSF
.391 U2CRRV U2UWD1;RSF 389 U2MST U2LE.RSF 389' U2MST U2LW.RSF:
389 U2MSTU2UE.RSF 389 U2MST.U2UW..RSF.
387 U2MSU2LE.RSF
-387 U2MS U.2LW..RSF 387 U2MSU2UE.RSP
- 387 U2MS U2UW.,RSF 393 U2PASSV U2LE..RSF 393 U2PASSVU2LW.RSF 393 U2PASSV Tu2uE.RSF 393 U2PASSV _U2UW.RSF 389 U2STGU2LE.RSF 389 U2STGU2LW.RSF 389.U2STGU2UE...RSF 389 U2STGU2UW.:RSF.
947,654 bytes 37 File(s)
Directory ot D,:\\Inppts and. Outputs\\u1+/-T2\\CFD 12/22/2003
.12/22/2003 09/09/2002
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- 09/09/2002 09/09/2002
.03:I0 03:10 01:1I0 01:10 01:10 01-:10 017:A0 01:i10 o0:10 01: 10 PM PM PM PM PM PM PM PM
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11, 168 11, 168 11, 168 11, 168 11,168 11, 168 11, 168 UIMSU2LE.CFD DIMS U2LW.,CFD UIMSU2UE-CFD UiMSU2UW. CFD UIR U2.LE.CFD UiRD2LW.CFD UIRU2UE.CFD UiRDU2TW, CFD Page 34 of 37
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Co Stellation Nuclear Services Calculation No: NMPAST-02-001 Rev. 2 Date: December 22, 2003.
09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 12/22/2003
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11,168 U2CRRVU2UW.CFD I,16A U2MS. _T2 E.CýFf 11,168 U2MST U2LW.CFD f,18 Tj2MqTU2UF.CFD 11,168 U2MST U2UW.CFD i C,1A t2M5 _U2LEý CFD 11,168 U2MSU2LW..CFD 11,168, U2MSU2UE.CFD 11,168 U2MS U2UW.CFD 11,168 U2PASSVU2LE.CFD 11,168 U2PASSV.U2LW.CFD 11, 168 U2PASS V_U2UE.CFD 11,168 U2PASSVU2UW.CFD.
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SC stellation Nuclear Services
- Calculation No-: NMPAST-02-001 Rev. 2 Date: December 22, 2003 09/09/2002 09/09/2002 09/09/2002 09/09/2002 09/09/2002 o09/0o9/2002 09/09/2007 01:12 PM
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AI YS7 CORPORATION
- NISYS-1,69-OVOO/RO Nine Mile Point NuclearStation DESIGN VERIFICATION OF CALCULATIONS. NMPAST-01 -001 AND NMPAST-02-001 August, 2003 Prepared by NISYS Corporation 4227 Pleasant Hill Road Building 15 Duluth, GA 30096-1619 Prepared for Nine Mile Point "Nuclear Station, LLC Lycoming, NY
08/25/2003 18:11
.:61646634B8 Aug-21.5-03 17:08 NIl*Y5 Corpov
-tion PAeE: '01
'P.03 770:*97 86642
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'Nine MLWPObint N~w~ern Lhiwen Deigs verlflcadom of Cale"WitOnsz
ýNAfPAST.&-I-OO)W afdNPAST-d2 Off CORPMEA TMJ APPROVALS 440,- T/~~
'propred by Duane T. kakahata PhD. PE R viewed by TU.aroU APProvWdby John P.Durhamn. PE Date Date SPage 2 of 12
Nine Mile.Point Nuclear Station Design Verification of Calculations' NMPASTO 1-OO Iand NMPAST-02-.001 NISYS-1: 169-DVOO RO V NIYS APPROVALS Prepared by Duane T. Nakahata, PhD, PE Y' '~/c~
Date R6viewed by T. M.-Carroll
- 2 Z)11-Date Date Approved by John P. Durham,*PE Revision level Summary of Change(s) 0Initial Issue:I I1 Page 2 of 12
~'
~-4~e?
Nine Mile Point Nuclear Stotion Des.ign: -Veniftcation. of Calcukitions NMPAST-OIO01 and NMPAST.02.001 NISYS-1169-DV001/R0 9q V
CORPWRATION1 2.0 2;Q 3,0 4.0 5.0 Table of Contents OBJECTIVE.....................................................................................................................
4 METHOD AND EXTENT OF DESIGN VERIFICATION...........................
I.....,5 REFERENCES.................
RESULTS.........................................................................................................................
7 RECOMMENDATIONS.,.............
12' ATTACHMENTS ATT No.
D%$crpiptin No. of Pages 1
Design Verification Criteria: (NMPAST-010-001) 1 2
Design Verification Criteria (NMPAST-02-001) 1 3
Certificate of Conformance 1
Page 3 of 12
Nine Mile, Point Nuclear Station Design Verification of Calculations N
NMPAST-O1-OOl and NMPAST-02.001 NISYS-1169-DVOO1RO 1.0 OBJECTIVE Theobjective of this report is to perform a design verification of Nine Mile Point:Nuclear Station (NMP) calculations NMPAST-01-001, Rev. I (Ref. 1) and NMPAST-02-001, Rev.
1 (Ref. 2).
Using the PAVAN *computer program (Ref. 3), calculation NMPAST-01 -001 determines
.the atmospheric dispersion coefficients (X/Q values) at the exclusion area boundary (EAB) and low population zone (LPZ).boundary, due to releases from specified Unit 1 and Unit 2 sources. Calculation NMPAST-02-001 uses theo ARCON96 program (Ref. 4) to determine the.X/Q values for the NMP;Unit 1 and Unit 2 fresh air intakes, due to releases
,from specified Unit 1 and Unit 2 sources. Atmospheric dispersion coefficients are needed to perform Alternative Source Term scoping calculations, which are documented
- elsewhere..
Page 4 of 12
Nine Mile Point. Nuclear -Station Design Verification of Calculations S
NMPAST-O1-001and:NMPAST-02-001 CO*RP0HA7OrN NISYS 1169-DVOO1RO 2,0 METHOD AND EXTENT OF DESIGN VERIFICATION The design verification process is described in NMP's Design'Verification procedure (Ref.
5), and in NISYS Corporation's Project Instruction (Ref. 6). The design review method, as defined in Reference 5, will be used to perform the verification of calculations NMPAST-01-00i and NMPAST-02-001...
The extent of the design review will include identification of the design input, calculation process, and output for the subject calculations. The design review will also evaluate the appropriate use.of the PAVAN and ARCON96 software to accurately determine the X/Q values. In addition, the following questions wjillbe addressed (as required by References 6 and 7) to,ensure: that relevant items are considered in the verification effort:
- 1. Were the inputs correctly stated?
- 2. Are the assumptions necessary to perform the calculations adequately described and reasonable?
- 3. Was an appropriate method used?
.4. Were the inputs correctly incorporated into the calculations?
- 5. Are the outputs reasonable compared to the inputs?
- 6. Do the :calculations conform to USNRC Regulatory Guides 1.145 and 1-.194?
The results of the design review are discussed.in Section 4.0. Completed ýdesign verification criteria sheets as required by
Reference:
6:are provided as.Attachments 1 and
- 2. As required by Reference 7, a Certificate of Conformance, signed by NISYS Corporation's Quality Assurance Manager is provided asAttachment 3.
Page 5of 12
Nine M&l ýPoint Nuclear Station N
SY Design Verificationof Calculations NMPAST-O1-OO1 and NMPAST-02-001 O I0.)APOR'TION NISYS-1 169-;DV001/R0
3.0 REFERENCES
- 1.
-Calculation NMPAST-01-001, Revision 1, Calculation of X/Qs at the EAB and LPZ from Releases atuNMP Units 1 and 2.
- 2.
Calculation NMPAST-02-001i, Revision 1, Calculation, of Atmospheric Dispersion
'Coefficients (X/Qs) at the NMP Unit 1 Technical Support Center and Units 1 and 2 Control Room Intakes for.All Releases.
- 3.
CCC-445, RSIC :Computer Code :collection -
PAVAN, NUREG/CR;2858 (November 1982), PAVAN: An Atmospheric Dispersion Program for Evaluating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations.
- 4.
CCC-664, RSICC Computer Code.Collection-ARCON96, NUREG/CR-6331, Revision 1
'(May 1997), Atmospherico Relative Concentrations in Building Wakes.
- 5.
Nine 'Mile Point Procedure NEP-DES-07, Revision 4, Design Verification.
- 6.
NISYS Corporation Project :Instruction, NISYS-1 169-PI00.1/RO, Performing 'Design Verification of Atmospheric Dispersion Calculations.
- 7.
Nine'Mile Point:Purchase Order ýNo. 03-45612, Independent Verification of Calculations NMPAST-01-001 and NMPAST-02-001, dated 7/1/2003.
- 8.
U.S. NRC Regulatory Guide 1.145, Revision 1 (February 1983), Atmospheric Dispersion
- Models for Potential Accident Consequence Assessments
- at Nuclear Power Plants.
- 9.
U.S. NRC Regulatory Guide 1.194 (June 2003), Atmospheric Relative Concentrations for
'Control Room Radiological Habitability Assessments at Nuclear Power Plants.
- 10.
NMPAST-01-001-CD (9/6/2002), CDR compact disc containing computer files for
'NMPAST-01-001, RevisionA1.
- 11.
NMPAST-02-001-CD (9/6/2002), CD-R compact: disc containing computer files for NMPAST-02-001, Revision 1
- 12.
NMP Unit 2 USAR Figure 2.1-2, Revision 15 (October 2003), Site Boundaries and Transportation Routes.
- 13.
NMP Unit 2 USAR'Figure 2.1-4, Revision 6 (April 1994), Low Population Zone Boundary.
- 14.
NMP Unit 1 LUSAR Figure 111-10, Revision 14 '(June 1996), Reactor Building and Turbine Building Cross-Section.
Page 6 of 12
,Nine Mile Point Nuclear Sta~tion Design Verification of Calulations IS NMPAST-*1-O01 and NMPAST-02-001 RPORArloV NISYS-1169-DVOO1/RO 4.0 RESULTS Design Verification Checklist Document:NMPAST-01 -001, Rev. 1. Calculation of X/0s at the Design Verifier's Name:
EAB and LPZ from Releases at NMP Units 1 and 2.
Duane T. Nakahata ReView Check Items Addressed with. Basis of Review Answer Yes Check YesTNO N/
Were the inputs correctly selected?
X 1 a.
6In MPAST-O1.001, the EAB distances from Unit 1 and Unit 2 for the E, ESE, and SE sectors may be in error, since, as defined below, the Exclusion Area should include NMP-controlled property: only. These distances appear to be measured to the eastern boundary of the neighboring Fitzpatrick site (i.9 and 1.6 km for, Units 1 ýand 2, respectively forthe E sector), rather than to the eastern boundaryof the.
NMP site (approximately 0.7 km for Unit 11 (Ref. 12)).
Per 10CFR100.3, Exclusion area is defined as "that area surrounding the reactor, in which the reactor licensee has the authority.to determine all activities including exclusion or removal of personnel and.property from the area. This area may be traversed by a highway, railroad,:oir waterway, provided these are not so close to the facility as :to interfere:
with normal -operations of the facility and provided appropriate and effective arrangements are made. to control traffic on the highway,
-railroad, or waterway, in case of emergency, to protect thepublic health and safety. Residence within the exclusion area shall :normally be prohibited. In any event, residents shall be subject to ýready removal in
ýcase of necessity. Activities: unrelated to operation of the reactormay be permitted in an exclusion area under appropriate limitations, provided that no significant hazards to-the public health and safety will result."
7lb.
Although the values-used for design inputs are referenced I (in, Section 5.1 of the calculation), for clarity of the geographic relationships it is recommended that the calculation include a scale drawing that shows: a compass "rose" superimposed upon an outline of the extent of: the EAB and LPZ. Alternatively, it is recommended: that the appropriate figures from the references be included as attachments-to the calculation.
11c.
The source of the meteorological inputs is clearly specified in Section
.5.1 of the calculation. However, the method used to obtain these inputs from the raw data is.not stated. Section 1.1 of Regulatory Guide 1.145 requires that meteorological data represent hourly averages, and are categorized into atmospheric stability classes according to Regulatory Guide 1.23 (now Safety Guide 23), 'Onsite Meteorological Programs". It is recommended that a statement documenting conformance to Safety
'Guide 23 be included.
Page 7 of 12
Nine Mile Point, Nuclear Station 7
Design Verification of Calculations NMPAST-O1-0O01 and NMPAST-02-01)
Document: NMPAST-01 -001, Rev. 1 Review Check Items Addressed with Basis of Review Answer Yes -No N/A 2,
Are the,assumptions necessary to perform the calculations X
adequately described and reasonable?
2a.
In Section 5.2.2 of NMPAST-01 -001, thedivalue used for the variable A,
'the minimum' vertical *cross-sectional area of the Unit :1 containment structure (2082 M2), could not be verified. As a check, the height:of the Unit 1' Reactor building is 42.2 m (Table :5.1-1.b of NMPAST-01-001),
and the horizontal dimension of the Ul RB-TB complex (east-west) is 99.67 m (Sect. 6 of NMPAST-02-001), yielding a cross-sectional area of approx. 4186 im2, The inputs for this assumption and a justification should be clearly stated. '(For example, "Although the actual cross-sectional area is __ m2,found by multiplying a height of -
m by length
,of __ m, a smaller area is assumed because the reactor building is connected to other buildings and this conservatively results in higher X/Q values.)
- 3.
Was an appropriate method used?
X 3a.
In Section 6.2 of NMPAS!-o1-001, the reason for hand-checking 28 sector 0.5% X/Q values is not clear. (Recommend that an example beýý provided to clarify the screening process!) Of these 28.° cases, 26 resulted in 0.5%.X/0 values' identical to the PAVAN output. However, the X/Q values subsequently.,calculated for the intermediate.time intervals differ from the PAVAN output. The differences are small (on the order of
.1%) and are apparently due to calculating the intermediate time~intervals using 3 significant digits (handccheck values) instead of 4 (PAVAN values).
3b.
Of the 28 hand-checked cases discussed in Section 6.2 of NMPAST '001, -.two.,cases resulted in a change to the reported value (from 2.048E-6 to 2.08E-6 for Unit 1 Main Stack to LPZ-E, and from 9.140E,5 to 9.58E-5 for Unit 2 Combined Vent to EAB-WSW), These modifications, which are conservative, appear to be due to differences between PAVAN and the hand-check procedures that derive. the upper envelope of the X/Q values versus their cumulative frequency of occurrence. :For the PAVAN approach,: :Section 4.6 of NUREGICR-2858 states, "Starting with the highest X/Q value, [subroutine] ENVLOP compares the slope of the line drawn from this point to every other point within an ~increment containing ten X/Q values." The FORTRAN listing was checked to verify that ENVLOP uses only ten points in each increment,'thereby calculating the slopes ofnine lines. In contrast, the EXCEL spreadsheets that document the manual 'procedure use eleven points per increment, resulting in ten slopes.
3c.
In Sections 6.2 and 6.3 of NMPAST-01-001, when calculating the intermediate time-period X/Qs using Alogarithmic interpolation, it is recommended that the basis for using the,selected time points of 8, 16, 72 and 624 hours0.00722 days <br />0.173 hours <br />0.00103 weeks <br />2.37432e-4 months <br /> (as shown in the Intermediate Time Calculations spreadsheets). be stated.
Page 8: of 12
Nine Mile Point Nuclear Station Design V verircation -of Calculations NMPASTOi..001 and NMPAST-02-061 NISYS1-1-69-.DVOOI/RO VNISYS5 COARPORATION Document: NMPAST-01 -001, Rev. 1 Review Check Items-Addressed with Basis of Review Answer Yes
'No N/A
- 4.
Were the inputs correctly incorporated: intothevcalculations?
X
- 5.
Are the outputs reasonable compared to the inputs?
X 5a.
Although the PAVAN computer input files, output files and Excel worksheets that are described in the each of the. calculations are provided on a read-only CD (Ref. 10)., it is recommended that a detailed listing of the files be, provided. This willassure that the files available on hand and those discussed in the calculation are identical.
- 6.
Does the calculation conform' to USNRC Regulatory Guide X
(RG) 1.145?7 Page 9,of 12
Nine Mile Point Nuclear Station Design Verification of Calculations NMPAST-O1-OO1 and NMPAST-02-.O0 NISYS-1169-DV001/R0 7
sis Desiqn Verification Checklist Document: NMPAST-02-001, Rev. 1, Calculation of Atmospheric Design Verifier's Name:
Duane T. Nakahata Dispersion Coeff icients (X/Qs) at the NMP Unit 1 Technical Support Center and Units 1 and 2 Control.
,Room Intakes for All Releases items Addressed with Basis of Review Answer ReviewCheck YesI No INA I
-~
1.,
Were the inputs correctly selected?
1 a.
Although the values uised for design inputs are referenced (in Sections 5.2 and 7.1 of the calculation), for clarityof the geographic relationships.
it is recommended that the calculation include a scale drawing that shows a compass "rose" superimposed upon an outline of the Unit 1 and
- Unit 2 showing the release points and intakes. Addtionally, it is recommended that the appropriate tables and figures from the references be included as attachmentslto the calculation.
l b.
The. source of the meteorological inputs Jis clearlY specified,in Section 5A1 of ýthe calculation. However. the method used to obtain these inputs from the raw data is not stated. Section 3.1 of Regulatory. Guide 1.194 requires :that meteorological data *represent hourly: averages, and are categorized into atmospheric stability classes according to Safety Guide 23 (formerly Regulatory Guide 1.23), "Onsite Meteorological Programs".
It is recommended that a statement documenting conformance to Safety Guide 23 be included.
X
- 2.
Are:the assumptions necessary to perform the calculations X
adequately described and reasonable?
2a.
In Section 6, the justification for all assumptions should'be-clearly stated.
For example, "Unit "1 releases to Ul OR intake building wake area is assumed to be one-half of the E-W U0 TB cro.ss-sectional area because
[give reason] and this conservatively results in higher X/Q values."
As another example, "U2 Main Stack release isa assumed to. be a ground-level release in ARCON96 because [give reason], as described in Section 7.3."
- 3.
Was an appropriate method: used?
Page 10 of 12
Nine Mile:Point NuclearStation Design Verification of Cakculations NMPAST-01-01 and NMPAST-024O01 NISYS-1169.-DV001/R0 SNIS YS Co*1,ORAATIo Document: NMPAST-02-00, Rev. I Review Check Items Addressed with Basis of Review Answer Yes No NIA
- 4.
Were the inputsvcorrectly incorporated into -thecalculations?
X 4a.
- In NMPAST-02-001, three conversions from English into metric:units are incorrect. In Section 5.4, the Unit 2 :RB outer radius (85' 6") should be
.26,06 m (not 25.06im). In Section 6, the:Unit 1 TB E-W dimension (327')
-should be 99.67 m (not 111.86 m), and the Unit 1 CR intake height above grade (72') should be 21.95 m (not 29.95 m). These errors are carried forward into Section 7.2, resulting in six errors in the Table 7.2.1 Building Wake Areas; Unit 1 (all) to Unit 1 CR should be 550. not 167 M2.
U2:(all except stack):to Ul CR should be 623 not 281 m2 U2 stack to Ul CR should be 2165 not 1363 i 2
U2 stack :to Ul TSC should be 3639 not 3549 M:.
U2 stack & SGB to U2 CR (all), should be 1844 not 1773 mn 2 :
U2 PASS to U2 CR (all);should be 922 not 886 in2.
The errors were carried forward into the ARCON96 computer runs.
- 5.
Are the: outputs reasonable compared to the inputs?
X 5a.
Although the ARCON96 computer.input files, output files and Excel worksheets that are described in 'the each of the, calculations :are provided on aread-only CD (Ref. 11), it, is recommended that a detailed
.listing of the files be provided. This will assure that the files available on
,hand and those discussed in the calculation are identical.
- 6.
Does the calculation conform to USNRC Regulatory Guide X
(RG) 1.194?
Page 11 of 12
Nine Mile Po0n Nuclear.Station Design Verification: of Calculations
/ NICS YS NMPAST-OI-O01 and NMPAST.02-O01 C 4YRPO)I NTION NISYS-1169-DVO00/RO 5.0 RECOMMENDATIONS,
- 1. Correcteor address the errors discussed in Item la (for NMPAST-01-001) and Item 4a (for NMPAST-02-001).of Section,4. Correct the affected computer input files and rerun them.
- 2. Improve.the justification for assumptions used in the calculations, as described in Item 2 (for both calculations) of Section: 4.
- 3. Evaluate the recommendations discussed in Items 1 b, 1c, 3a, 3c, and. 5 (for NMPAST-O1 -
001), and Items 1 a, 1 b, and '5(for NM PAST-02,001) of Section 4.
- 4. Review the results of the hand checks described in Item 3b (for NMPAST-01-001) of Section 4, Revise the hand checks'to remove conservatisms, if desired.
- 5. Revise NMPAST-01 -001 and NMPAST-02-001, incorporating changes due to the recommendations stated above.
Page 12:of 12
DESIGN N
VERIFICATION CO woRTIoN I
NISYS-1169-DV001/R0 CRITERIA..
J 1. Originatorfollowed :defined procedures.
1 2. Title, purpose, and function of thework checked are adequately described.
1 3. Work method is.-clearly stated and appropriate.
[
- 4. Assumptions are identified.
Open items are flagged for subsequent verification where
'necessary.
- See Item 2, oLSection 4;0 I
5i Technical bases and references are current and are correctly selected and incorporated.
-' 6.. Design inputs are properly selected and adequately, identified.
Any specific :inputs ýto be excluded are adequately identified.
See Item 1 ofSection 4.0
,1
- 7. Applicable codes, standards, and regulatory requirements are identified andproperly used.
S8. Analytical steps can be verified without recourse to originator, 9 9 Each page of the work is identified and traceable tooriginator, date, andproject or equivalent control "number.
Z 10.-Allrmarkings are legible and identifiabic.
"l 11. Work clearly references any final supporting cmputer luns. Caic. needsxihdexof combuter files I
- 12. Final computer runs or documents being checked include input listing. Correct inputs are used.
Where input is not listed on output, alternate methods are used by thechecker.
'Z 13.. Final computer runs arc uniquely idcntified.
I
- 14. Results areconsistent with inputs., technical procedures, and other project criteria.
4 15. Results are reasonable.
[
- 16. Revisions are clearly documented.
I
- 17. Technical interface requirements in the Project Plan have beensatisfied.
- 18. Appropriate QA requirements are specified.
E] 19. Applicable construction and operating experience has been considered.
N/A El 20. Specified parts, equipment, and processes are suitable for required application.
N/A El 21. Specified materials are compatible with each other and the design environmental conditions to
.which the material will be exposed.
N/A El 22. Adequate maintenance features and requirements are specified.
N/A El :23. Accessibility and otherudesign provisions are adequate for performance of needed maintenance.
and repair.
N/A El 24. Adequate accessibility is provided to perform the in-service inspection expected to be required during plant life.
N/A El 25. Design properly considered radiation exposure.to the public and plant personnel. N/A
'- 26. Acceptance criteria incorporated into the design documents are sufficient to allow verification that desi gn requirements have been satisfactorily accomplished.
N/A El 27. Adequatebhandling, storage, cleaning, andshipping requirements arespecified.
N/A El 28. Adequate identificationwrequirements are specified.
N/A Design: Verified-Calculation-NMPAST-01 -001, Revision:
1 Verifier-
'~i~
'Date:
414-f
- 7 NISYS QA Form 3.2 (JUL-2002)
Page I of I
DESIGN YS I
VERIFICATION CORP ORATION NISYS-1169-DVOO1/RO CRITERIA 1 1. :Originator followed defined procedures.
- 2, Title, purpose, andfunction of the work checked are adequately described,
[
- 3. Work method is clearly stated and appropriate.
1 4. Assumptions are identified.
Open items are flagged for subsequent verification where necessary.
See Item,2 of Section 4.0 1 5. :Technical bases and references are current and are-correctly selected and incorporated.
0i
- 6. Design inputs are properly selected and adequately identified.
Any specific inputs to be
ýexcluded are adequately identified.
See Item 4 of Section 4.0
[
- 7. Applicable codes, standards, and regulatory requirements areidentified and properly used.
[
8 Analytical steps can-be verified without recourse to originator.
1
- 9. Each page of the work is identified and traceable to originator, date, and project or equivalent control number.
1
- 10. All markings are legible and identifiable.
Mi 1 LWork clearly references any final supporting computer runs. Calc. needs index of cOmputer files
' 12. Final computer runs or documents beingcehecked includelinput listing. Correct inputs areused.
Where input is not listed on output, alternate methods are used by the checker.
1 13. Final computerruns are Uniquely identified.
S-14 Results are consistent with inputs, technical procedures, and other project criteria.
S15. Results~are:reasonable.
'1
- 16. Revisions-are clearly documented.
'Z 17. 'Technical interface requirements intheý.Project Plan have been satisfied.
S:18. Appropriate;QA requirements are specified.
F-19. Applicable construction and operating exriencehas been considered.
N/A F-1 20. Specified parts, equipment, and processes are suitable for required application.
N/A Li 21. Specified materials arecompatible with eachother and the design environmental conditions to which the material will be exposed.
N/A Li 22. Adequate maintenance features and requirements are specified.
N/A Li 23. Accessibility and other design: provisions are adequate for performance of needed maintenance andrepair.
N/A Li 24. Adequate accessibility is provided to perform the in-se rvice inspectioni expected to be required during plant life.
N/A, Li 25.'Design properly considered radiation:exposure to the public and, lant personnel. N/A Li 26. Acceptance criteria incorporated into the design documents are sufficient to allow verification that design requirements have been satisfactorily accomplished.
N/A Li 27. Adequate-handling, storage, cleaning, and shipping req uirements are specified.
N/A L 28. Adequate identification requirements are specified.
N/A Design Verified:
Calculation NMPAST-02-O01 Revision:
i Verifier.
7J A~
Date:
/5 NISYS QA Form 3.2 (JUL.2002)
Page I of I
CERTIFICATE OF CONFO NCE I
NISYS-1169-DVOO1/RO COC Number: C0C1169001 Date: 8/2512003
ýClient: Nine Mile;Point Nuclear Station, LLC NISYS ProjectNo.:: 1169 NISYS Project
Title:
Nine Mile PointCalculationDesign Verification Contract No/Date: 00750 /R 11/07/01 P.O. No/Date: 03-45612107/01/03 Supplier: NISYS Corporation NISYS.Corporation certifies that the materials and products listed below were furnished:to CLIENT in conformance with the reuirements of Purchase Order'.
03-45612 Customer NISYS Item No.
Item No.
Ohity.
Item / SerViceeDescription 001.
NISYS-1 69-DV-1 Design Verification of Calculations NMPAST-01-001 and 00I/R0 NMPAST-02-001 Prepared by:
Duane T. Nikahata, PhD, PE
-(First,: MI, Last)
Prujuct Engincer 7
Printed] Typed Name and Signature.
Date Title NISYS:QA Manager
'Mark R. Winsor, PE (First, MI, Lat)__________
Printed, ITyped Name
/
Signature Date NISYS QA Form 2.1 (JULy2002)
Page I of 1,