Text

Calculation for Alternative Source Term, H21C076, X/Qs for Releases from NMP Units 1 & 2 (CNS Calcs NMPAST-01-001 & NMPAST-02-001)
	ML070110321
Person / Time
Site:	Nine Mile Point
Issue date:	03/22/2004
From:	Gardner S, Heffner J; Nine Mile Point
To:	; Office of Nuclear Reactor Regulation
References
	H21C076
	Download: ML070110321 (106)
	v • d • e

Nine Mile Point Unit 1 Alternative Source Term Calculation H21C076 "X/Qs for Releases from NMP Units 1 & 2 (CNS Calcs NMPAST-01-001 & NMPAST 001)"

Project: NINE MILE POINT NUCLEAR STATION Unit:(1,.2 or.0=Both): 0 Discipline,: ANALYSiS Title Calculation No.

X/QSFOR RELEASES FROM NMP UNITS 1 &2 (CNS.CALQS H210 076 NMPAST-01-001"& NMPAST.02-001) (Sub)system(s)' Building Floor Elev. Index No..

N/A I N/A I N/A N/A originator(s)

JAMES HEFFNER (C57133) SHANE.GARDNER (C57133)

Reviewer(s) / Approver(s)

S GARDCNER (C57133),J HEFFNER (C57133) /T NEIDER (CNS) SEE.REMARKS GLENN STINSON - NMPNS Eval., DER, or Prep'd Reviewed Rev Description Change No. Date By Date A Date 00 ORIGINAL ISSUE N/A ___1.2______ 1____

Computer Output/Microfilm Filed Separately (Yes I/No NA): No :SafetyClass (SR / NSR /Oxx) : SR Superseded Document(s) : NONE Document Cross Reference(s) - For additional references see page(s).:SEE PAGES 29, 78,379A&97 Ref Doc No Document No. Type, Index Sheet Rev General Reference(s):

SEE PAGES29, 78, 79 &97 Remarks:

CNS CALCULATION NMPAST-01-0W1 CALCULATES X/Qs AT THE EAB,& LPZ (SEE PAGES 3 THRU 50)

CNSCALCULATION NMPAST-02-001 CALCULATES XIOs FOR CONTROL ROOMS & TSC (SEE PAGES 51 THRU 90)

THESE CALCULATIONS WERE INDEPENDENTLY REVIEWED, AND VERIFIED IN ACCORDANCE WITH NEP-DES-07, BY NYSIS CORP (NI 3617) (SEE PAGES 91 THRU 106)

NOTE: PAGES 23, 24 & 81 CONTAIN COLORPRINTING. NO INFORMATION IS LOST IN BLACK & WHITE.

Confirmation Required (Yes,I No) : No IFi'nal Issue Status: :1Turnover Required

.See Page(s): . . .IAPPI (Yes / N/A ): N/A 1:0CFR50.59 Evaluation Number(s): N/A COmponent ID(s) (As shown in MEL):

Copy of Applicability Determination or 50.59 Screen N/A Attached? Yes-I No n Key Words,: XOQ,. ATMOSPHERIC DISPERSION, EAB, LPZ, CONTROL ROOM, TSC, PAVAN, ARCON96

\\NAS-NMAP-01\E48425\U1 CALCs\0a1076\H2lCO76Cov.doc E-DSO NEP-DES-08 Rov 06

3 Calculation Cover Sheet CalculationNo... NjgAST-0l-00! Rev., 2 No. of Pages 45 Title Calculation of X/Os at the BAB and LPZ ýfror Releases at NMP Units I and 2 Rev. 0 Name ISignature I Date .1 Lrepared By James.Hef eZrZ,_._......

Checked BY, Shane Gardner ___...

Approved B y Tara Neider ... ._

Rev. , Name. signI atu= Date, P repare d a " J a me s.H e ffh er _ _. ... _ ._ _,,,....

Checked By Shane Gardner .. .. . .. ..

Approved"By> . .. TWaraNeider I ..-.

'Description of Changes New meteorological (MET) data is :irncorporated.

o Rounding errors contributed to minor discrepancies in results of NMPAST'0l001, o All calculations ywere rerun in PAVAN Using nmw MET dat&

The WSW is regarded as a land rather than coasial sector for NMP Unit 2:in this revision.

o Main Stack distance to EAB was changed from 405 m to 1,615 rn.

o Combiod Radwasti/Reactor: Building Vent was changed from 747 m to 1,381 m.

Eliminated t coastaltsector distances to EAR.

o..W, WNW NW, NNW,:N, NNE, NE, and ENE sectors are-considered coast and arenot cofisidered for evaluation in this revision.

o. Coastal sector distances to EABwere substituted wilh the minimumland sector distances to obtain overall site X/Q values.

Provided additional calculations for stack releases in each sector to prove that m Intmum X/Q c0ncentrations do.not occur at distances beyond the EAB and LPZ.

o RG 1.1 45 Rev. I mentions that XIQ values may occu at distances' beyond the EAB and. LPZ..

o PAVAN runs were performediat various distances ranging fiom 100-9,000 n for stack releases to prove that maximum X/Qs exist afthe EAB and LPZ.

Affected Pages - Sections 5through 9.

CNS QA Form: OA-3.2.I, Rev. 0

(4.

Rev. 2 Name:. Si nature Date eced3B Shane.MGardner Checked BY David.'Matchick 6z Description of Changes - /

The purpose of thisrevision is to respond to comments made in a third party reviewperformed by NISYS Corp. at the request of NMPNS. Several comments were made and the.*rcucd is referrd to tie NISYS idocument NISYS-1 169-DVOOI/RO for more detail CNS and NMPNS agreed' to a plan to reýlve a selection ofthe NISYS comments (see CNS-03-218, 9/24/03 and electrunic conrrsptmdroc from Timothy iM. Kurtz to Shano.Gardnter, November 6. 2003, "Re: CNS Comments on NISYS Review of XIQ.

Calculations"). CN$*.13-218 provides a cescriotion regarding hoW the commnots vwer addroskd and provides the basis for incorporating the comments into this calculation. More specificWally theffollowing.

comments were addressed:

NISYS Comment No, Da*¢rtpon A fftcced Page(s)

b. include a scale drawing.(compass -rose'") Appendix A Ic statement documenting conlfdrmancc to Safety Guide 23 3-4, 24.(Ref. 21) 2a jutification of PAVAN variable "A".(building wakearea), 6, 24 (Refs. 19 & 20) 3b correi and review of 28:hand-chhccked 0.5% X/iQ valucs 16-17, 19-22 N, provide a basis for intermediate time points. 17 Sa add a.detalied listing of fies on CD be pixovided Appendix C Resolution of NISYS comment 3b resulted in minor chang.s to the rrsults provided in section 7. More

.specifically, it was detetniined that PAVAN outputs werecorrectly'processed internally to the code

(EN VLOP routine) nid tharfonc tl results in the output files were correct. Tbhe results tables in section 7 were updated to reflect this finding Thc new results wero'only slightly different from the.results of

,previouarvsian sI.L ItI addidtio to the changes ind iatedabove, the calculation was. further revised to Jncorporate wor editorial changes Affected Pageýs:Calculation Cover Sheet: (Title);.all pages thereafter CNS. QA Form:QA-3.2. Rev. 0

Calculation Review Checklist Calculati~ono P14P43-f-2)I0o6'ev. ~_

Circle. as apprVorite., the Yes/No/NA for all items Correct calcuation format. ................... .................... NoNA Correctness Of assumprtions, ........... ............... ........................................... *No/NA Adequacy of assumption basis...................................... ................................ / N o/N A Cormctness ofoparameters used.......................................... .............. ( No/NA Appropriate choice of metho .......................................................... . No/NA Adequate documentation of method .. ................. .............. I....... q No/NA Correct application of method ........... ..................... ..... .............. ...... ....... No/NA Correctness, of resultsconclusions ................................................................... (R N o/NA Adequate Referencelist ................. ....................... ...................................... & Nq/NA If computer softwarewasvused to perform the calculation, the following elements shall alsp be considered:

Proper software verification and Verification documentation ........................ (No/NA Correctnessý of input parameters ..... . ........................ .qNo/NA I Correct information in analysis calculation ..... .... .. o/NA.

Correct interpretation of results ...... ...........

,..,. .. .. N/NA Signat e . .... 1 ...............

CNS QA Form: QA-3.2.2, Rev. 0

.hCorlls ~atiolnl Calculation No: NMPAST-O1-001

.. l ..o Rev.ý 2 Nuclear Services Date: Dec. 19,2003 Table of Contents

11. O bjective ................. .. ..................................................................................................... 3

2. Background ..................................................................................................... ..................... 3 2.1. Applicable Regulations and Commitments ...................... 3

3. Methodology ................ ........ ....... ..................... ,.................... ......... s............................. 4

4. Computer'HardwarelSoftware Usage ............................................................................ 5 4.1. Hardware Used .... ................... .......... e ..... ........... . ....................................... 5 4.2. Software Used ............................................................................................. ....... 5

5. Inputs and Assumptions ................................................................................................. 5 5.1. Design Input..................... .... ............................. 5 5.2. Assumptions ................................................. I.......... ................... 6.....................

6 5.2. 1 Release Point Distances to the EAB and LPZ.... ........ ......... .................... 6 5.2.2. Building Wake Correction Factors ..................... .............. 6 5.2.3. Site Topography...... . ..... ! ................................. 6 5 .2.4. Id entica l Data .. ........... ......................... ......... ........... ................................... 7 5.2:5. Maximum Category 12 Wind Speed. ........................................ ................................... 7 5.2.6. NMP Unit2 WSW Sector .... ................... 7 52.7. 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... ..... w............. ................ .................... ............. ......... 17 6.4. Results .......................................................... ....................................................... 4-17

7. Conclusions,............ . ............................................ 22

8. References .......................................................................................................................... 24 A ppendices ............................................................................................................................ 25 Appendix A -Figures: EAB and LPZ Regions Showing Associated X/Q Directions ......... 26 Appendix, B - PAVAN Output ................................................................................... ...... ,,,29 Appendix C- Listing of Files on DATA CD-ROM for Calculation NMPAST-0-001, ......... 42 Page 1 of 45

A C s aiCalculation No: NMPAST-01-001 C ~onstellation Nuclear Services Rev. 2 Date: Dec. 19, 2003 List of Tables Table 5.1-l.a PAVAN Input for.Unit I Main Stack Release; ........................ ....... ................. 8 Table 5.1-1.b PAVAN Input for Unit I Reactor Building Blowout Panel Release..;.......9 Table 5.1-1.c PAVAN Input forUnit 2 Main Stack Release... ............ ........... 10 Table 5.1-1.d PAVAN Input for.Unit 2 Combined Radwasteand Reactor Building Vent Release .... .. ...... .......... ... ..........

m ........ .. ..............s ...................... , ........................ ,12 Table 5.1-2-Card 9 Input ...................................................................................................... 13 Table 5.2-1 Input References for-Similar PAVAN Input Files..................... .............. 15 Table, 6.4-1 Nine Mile Point 0.5% Sector Dependent Short-Term XIQs Calculated with PAVAN ................ ............................................... 19 Table 6.4-2 Unit I Main Stack Non-Fumigation X/Q Values .............. ................ i .......... 20 Table 6.4-3 Unit I Reactor Building Blowout Panel X/Q Values ...................................... 20 Table -6.4-4 Unit 2 Main Stack Non- Fumigation X/Q Values ... ......................... a......... 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 ..................... 23 TableT-2 Elevated Release X/Q Selected for Evaluation at NMP ................. 23 List of Figures Figure 6.1-1 Unit I Main Stack X/Q Versus Distanzce ...... .......... 18 Figure 6.1-2 Unit 2Main Stack X/Q Versus Distance ..................................................... 19 Figure A-1 EAB: and Associated XIQ Directions.......... ........ ,.27 Figure A-2 LPZ and Associated X/Q Directions. ............... ............. w 28 Page 2 of 45

Calculation No: NMPAST-01-001

,Constellation Rev. 2 Nuclear Services Date: Dec. 19. 2003

1. Objective The purpose of this calculation is to determine conservative estimates of exclusion area boundary (EAB) and low population zone (LPZ) atmospheric dispersion coefficients (XýQs) for use in calculations 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. Background

NMP has requested the services of Constellation Nuclear Services (ONS) 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 of design basis accident dose consequences and can be applied to other calculations which determine radiation dose consequences at the EAB and LPZ boundaries.

After a postulated accident at the NMP Unit 1 or Unit 2, radioactivity may reach the.

atmosphere by several pathways. These pathways include the reactor building blowout panel,.

the turbine building blowout panel and the main stack for Unit 1. For Unit 2, the. release pathways include the combined radwaste and reactor 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 at the EAB and the outer boundary of the LPZ. The determination of atmospheric 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 1 Main Stack

. Unit :1 Reactor Building Blowout Panel

Unit 1 Turbine Building Blowout Panel

Unit.2 Main Stack

Unit 2 Combined Radwaste and Reactor Building Vent o Unit 2 Main Steam Tunnel Unit 2 Standby Gas Treatment- System Building o Unit,2 Post Accident Sampling System Panel 2.1. Applicable Regulations and Commitments

'PAVAN is used to determine X/Q values used in the assessment of dose consequences of design, basis accidents in nuclear power stations. 10 CFR Part 100 (Reference 6) and 10 CFR Part 50. (Reference 7) require such assessments, PAVAN follows the guidance of R.G, 1.145 (Reference 2) for calculating X/Qs. Meteorological data are hourly averages obtained from Page 3 of 45

C'" " Calculation No: NMPAST-01-O01 Rev. 2 Nuclear Services Date: Dec. 19, 2003 NMP.Joint Frequency Distribution Report (JFD) (Reference 9) and the analysis conforms to requirements of 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 atmospheric stability class. Wind direction is distributed. into 16 sectors. For each sector a 0.5% X/Q is calculated. to represent the 0- 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months X/Q.in accordance with R.G. 1.145 (Reference 2). The 0.5% X/Q is the value which is equaled or exceeded 0.5% of the time. PAVAN also calculates ia sector annual average X/Q in accordance with R.G. 1.111 (Reference 3). The 0 -2 hour XIQ 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 used to represent the 0 - 2hour 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,the annual average XIQ are used to determine 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 the 0 - 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time period. The highest X/Q value for the 16. sectors represents the maximum. sector X/Q.

The X/Q value for EAB or LPZ evaluations should be the maximum sector XJQ or-the/5%/

overall site X/Q, whichever is higher. A-more detailed description on the methodology used by PAVAN to calculate X!Qs is provided, in the reference documentation (References 2, 3 and 8).

Page 4 of 45

@ Constellation ConsellitionRev. Calculation No: NMPAST-01-0012.

Nuclear Services Date: Dec. 19, 2903 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-76 in accordance with the CNS QA Program (Reference 15).

4.2. Software Used The program PAVAN is written in FORTRAN IV computer language and is compatible with 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 was also used for :calculation purposes outlined in Sections 5.2.3, 6.1, and 6.2. In accordancewith the CNS QA Program (Reference 1), no computer code verification is required for Excel.

5. Inputs and Assumptions 5.1. .Design Input Table 5.1-1 summarizesthe design input used to generate the input files for the PAVAN calculations. The actual inputfiles for PAVANare included in the Input FileslfoIder 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 iVMP,60m JFD_1997-2001 for CNS'file on the enclosed CD. Complete descriptions and proper formats of each data

.input is included in the PAVAN user~s guide.(Reference 8). No tableS are provided for the following calculations:

" Unit1 Turbine..Building Blowout Panel

" Unit 2 Main Steam Tunnel

Unit 12 Standby Gas Treatment System Building unit 2 Sampling System Panel U

The reason for the omission of these tables is explained in Section 5.2.4.

The design inputs required for calculating the.off-site X!Qs using PAVAN were obtained from the following documents:

Accident X/Q Values for Nine Mile Point Unit 1 Releases from the Main Stack and the Reactor and Turbine Buildings (Reference 10)

Page, 5 of 45

A2VCalculation 11 No: NMPAST-O1-001 Rev. 2 Nulear 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 Drawing C-26658-C (Reference 12)

° NMP Joint Frequency Distribution Report (JFD) (Reference 9) o NMP Unit 2 USAR Figures 2.3-43 through'2.3-46 (Reference 1.3)

NMP Unit 2 USAR .Section 2.34.4.2 (Reference 14)

NMP Drawing C-18713-C (Reference 16)

NMP Unit 2 USAR Figure 1.2-11. (Reference 17) 5.2. Assumptions 5.2.1. Release Point Distances to the EAB and LPZ Due to the close proximity of the Unit 1 reactor building blowout panel with the turbine building blowout panel, identical distances to the. EAB and LPZ were used for each of these release points.

Due to the close proximities of the Unit 2 combined radwaste and reactor building vent, the main steam tunnel, the standby gas treatment system building and the post accident sampling system panel, identical distances to the.EABI and LPZ were used for each of these release points.

5.2.2. Building Wake Correction Factors For the cases involving ground level releases, the ssmallest vertical-plane cross-sectional area of the corresponding reactor building, in m2, wasused in accordance with R.G. 1.145.

(Reference 2). An area of 2,082 m2 was used (References 10, 1.9 and 20) for the Unit 1 releases classified as ground level, and ,ah area of 2844 m2 was used (Reference 14) for the Unit 2releases 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 distances with 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 represents roughly the entire distance from the stack.releases to the LPZ. 3,000 m wasselected since it represents roughly half of the distance.from the stack releases tolthe LPZ. Terrain heights foe all 16 sectors were provided in Reference 13 at various distances from the site. A Straight-line slope was assumed to exist between the terrain height at the site and the terrain height at various distances from the: site. The straight line slopes were used in Microsoft@ Excel to estimate the terrain heights at.3,000 m and 6,000 m. For any terrain height calculated as less than plant grade elevation, a terrain height of zero meters was assumed, since the height above plant grade level is called for in the PAVAN user's guide Page 6 of 45

Calculation No: NM PAST-01-001 Consteation Rev.2 Nuclear Services Date: Dec. 19,2003 (Reference 8). This: entire terrain height calculation, 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 NMP,, to affect the diffusion of radionuclides releases from the elevated main stacks, the default terrain adjustment.factors (TAF=1) were applied.

5.2.4. Identical Data For the reasons mentioned in Sections 5.2.1 and 5.2.2, several of the PAVAN input files, with the exception of file name, have the same input data 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 provided in Table. 5.2-1. Likewise, the output files for those mentioned in Table 5.2-1 are also assumed to be identical to their reference output files and are therefore not included in this report. These.files, both input 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. Maximum wind speed is required input for each wind category in PAVAN.

5.2.6. NMP Unit 2 WSW Sector The NMP Unit 2 WSW sector distance to the EAB may be considered as a land or coastal distance (Reference 11),. This calculation uses land distances to the EAB from the Main Stack and Combined Radwaste/Reactor Building of 1,615 m and 1,381 m, respectively.

5.217. Coastal Sectors The following sectors are regarded as: coastal and are not considered (Reference 18):

oW

WNW

,NW

NNW oN

- NNE oNE

ENE Page 7 of 45

Calculation No: NMPASTmO1-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19,2003 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-l.a PAVAN Input for Unit 1 Main Stack Release!

Card Variable Data Input Type Name 1 KOPT(1 4, 6, 0

_8 KOPT(7.9- 1

10) 2 TITLD(1-5) Nine Mile Point TITLD(6-10), 1101/97 to 12/31/01

"_TITLD(1 1-15) Elevated 1060-7 meters.

3 TITLD(16-!20)_ 60.7 m TITLD(21-25) 51.2 m 4 . TITLD(26-45) NMP Joint Frequency Distribution Report (JFD)

5 TITLD(46-65) Nihe Mile Point Unit 1 Main Stack to.EAB/LPZ 6 .NVEL 12 categories NDIS. 2 distances.

7 A 0 mG(.no input, needed for stack releases)

D 0, m (no input needed for stack releases)

HS 106.7 m TOWERH 60.7 m 8 CALM(J) 0 (for all sinceKOPT(8)=0)

.9 FREQ(K,I,J) See Table 5.1-2 10 UCOR -1 UMAX(l) 1=1,:0.44 m/s 1=7: 6.0 m/s 1=.2:10 m/s .8: 8.0 m/s 1=3:.2.0 m/s 1=9:10.0 m/s 1=4: 3.90 mrs 1=10: 13.0 m/s 1=5: 4.0 rn/s 1=1 1: 18.0 mis 1=6: 5.0 m/s I1=12: 60.5rm/s.

11 BDY(KI) K 1=11 (M) 1=2 (m)

S 2,000 6,116 SSW 1,500 6,116 SW 1,;200 6,116 WSW 830 6,116 W1830 6,116 WNW1 830 6,116 NW1 830 6,116 NNW' 830 6,116 N1" 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

~c~'r~ -~ ~, 14 Calcula.tion No: NIMPAST-O1-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003 Card Variable Data Input Type Name. ._........

SSE 2,000 6,116 12 TAF(K,l), K 1=1, 1=2 All 1,0. 1.0 13 DIST(KI) K 1=1 1=2 All 3000 m 6000 m

.14 HT(K,I) K 1=1 (m) 1=2 (in)

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 ESE 16 32 SE 11 22 SSE. 14 27 1 Represents a coastal sector,. The selected distance of 830 m represents the distance from the Unit 1. Main

$tack to the EAB in the WSW sector. The WSW sector contains the minimum. distance from the Unit 1 Main Stackto the EAB for all land sectors:

Table 5.14-.b PAVAN Input for Unit I Reactor Building Blowout Panel Release Card Variable Data Input Type Name 1 KOPT(1.4, 0 6, 8-,9)

KOPT(7,10) 1 2 TITLD(1-5) Nine Mile Point.

TITLD(6-10). 1101197 to 12/31/01

.TITLD.(11- Ground Level Release 3 TITLD(16- 60.7 m

.20)

TITLD(21- 5t1.2 m 25) 4, TITLD(26- NMP Joint Frequency Distribution Report (JFD) 45) 5 TITLD(46- Nine Mile Point Unit 1 Reactor Building Blowout Panel to EAB/LPZ 65) 6 NVEL 12 categories NDIS 0 distances 7 A 2082 m2 (per Reference 19and&20)

D 42.2 m Page 9 of 45

t14 7-LC-t%.- 5.t Calculation No: NMPAST-01-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19.2003 Card Variable Data Input Type Name HS 10m TOWERH 60:7 m 8 C0M*j) 0 (for ol! since KOPT(8)=0) 9 FREQ(K,I,J) See Table 5.1-2 10 UCOR -1 UMAX(I) 1=1: 0.44 m/s 1=7" 6.0 mIs 1=2: 1.0rn/s 1=8: 8,0 m/s 1=3: 2.0 rn/s 1=9: 10.0 m/s 1=4: 3.0 m/s 1=10: 13.0 m/s 1=5: 4.0 rn/s 1=1 1: 18.0 m/S 1=6: 5.0 m/s 1=12: 60.5 m/s 11 BDY(K,I) K 1=1 (meters) 1=2 (meters)

S 2,000 6,116 SSW 1,500 6,116 Sw 1,200 6,116 WSW 830 6,116 W1 830 6,116 WNW" 830 6,116 NW1 830 6,116 NNW' 830 6,116 N1 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 SSE 2,000 6,116, 12 TAF(K.I) No input required (KOPT(9)=O) 13 DIST(KOl) No input required (groUndljevel release) 14 :HT(KI)'_ No input required(ground level release).

1 Represents a coastal sector. The selected distance of 830 m represents the distance from the Unit 1 Reactor Building Blowout Panel to the:EA8 in theWSW sector., The WSW sector contains the minimum distance from the .Unit 1 Reactor Building Blowout Panel to the, EAB for all land sectors.

Table 5.1-1 .c PAVAN Input for Unit 2 Main Stack Release Card Variable Name Data Input Type 1 KOPT(I 4, 6,8) 0 KOPT(7,9-10) 1 2 TITLD(1-5) Nine Mile Point TITLD(6-10) 1/01/,97 to 12/31101 TiTLD( 1 1-15) Elevated."30.8 meters 3 TITLD(1 6-20) 60.7 m

..... TITLD(21-25) 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 NVEL 12 Categories Page 10 of 45

1 0 HLl C*76ým- ý ý Calculation No: NMPAST-01-001

- Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003

'Card Variable Name Data Input Type NDIS 2 distances_

,7 A 0 m" (no input needed for stack releases).

D ,0 m (no input needed for stack* releases)

HS 1:30.8 m TOWERH 60.7 m 8 CALM(J) 0 (for all since KOPT(8)=0) 9 :FREQ(KIJ) See Table 5.1-2 10 UCOR -_1 UMAX(l) 1=1: 0.44 mis 1=7: 6.0 m/s 1=2: 1.0 mIS 1=8: 8.0 m/s 1=3: 2.0 mIs 1=9: 10.0 m/s.

1=4: 3.0 m/s =110:. .13.0 m/s 1=5: 4.0 m/s 1=1 1I.18.0 m/s 1=6: 5.0.m/s 1=1.2:. 60.5 m/s 11 BDY(K,I) K 1=1 (m) 1=2 (m)

S 2,256 6,116 SSW 1,936 6,116:

SW 1,615 6,116 WSW 1,615 6,116 Wi 1,555 6,116 WNW 1 1,555 6,116:

NW 41,555 6,116 NNW' 1,555 6,116

N.4 1,555 6,116 NN E ...... 1.,.555_ ..........

- 6,116 NE' 1,555 6,116 ENE 1 1,555 6,116 E 1,555 6,116 ESE 1,555 6, 116 SE 1,600 6,116

-SSE 2,134 6,116 12 TAF(K.l) K 1=1 1=2 All 1.0 1.0 13 DIST(K I) K 1=1 1=2 All 3000 m 6000 m 14 H(K) =1 (m) 1=2(m)

S 28 57 SSW 19 39

_SW 19 394 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 ESE 16 32 Page 11 of 45

,k7 Calculation No: NMPAST-01-001

Constellation Rev. 2 Nuclear Services Date: Dec. 19,2003 Card Variable Name Data Input Type SE 11. .22 SSE 14 27 1 Represents a coastal sector. The seliected distance of 1,555 m represents.the distance fromn the Unit'"2.

ManSta.ktd the.EAB i thEe and ESE sectors. The E and .ESE *sectors* contain the minimum distance

from ýthe unit*2::Main Stack to.the EAB~for all land sectors.

Table 5.1-1 .d PAVAN Input for Unit,2 Combined Radwaste and Reactor Building Vent Release Card Variable Name Data Input Type ,o.....

1 KOPT(I-4, 6, 8- 0 9)_ _

KQPT(7,10) 1.

2 TITLD(1-5) Nine Mile Point TITLD(6;10) 1/01/97 to 12/31/01 TITLD(11-15) Ground Level Release 3 TITLD(16-20) 60.7 m TITLD(21-25) 51.2 m 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 EAB/LPZ

.6 NVEL 12 categories NDIS 0 distances.

.7 A 2844 m' D. 51.9 m HS ' 1n TOWERH 60.7 m 8 CALM(J) 0 (for all since KOPT(8)=0) 9 FREC(K,!,J) See Table.5-2 10 UCOR -1 UMAX(l) 1=1: 0.44rmls 1=7: 6.0 m/s 1=2: 1.0 m/s 1=8: 8.0 M/s 1=3: 2.0 mis 1=9: 10.0 m/s

,1=4: 3.0 m/s 1=10:13.0.mis 1=5: 4.0 mrs 1=11: 18.0 mis 1=6: 5.0 mls 1=12: 60.5 mis 11 BDY(KI) K 1=1* (meters) 1=2 (meters)

S 1,945 6,116 SSW 1,695 6,11.6 SW 1.381 6.116 WSW 1,381 6,116 Wi 1,381 6,116 WNW' .1,381 6,116 NW' 1,381 6,116 NNW' 1,381 6,1!6 N1 1,381 6,11.6 NNE' 1,381 6,116 NE1 1,381 6,116 ENE 1 1,j381 6,116 Page 12 of 45

Calculation No: NM PAST-01-001 Constellation Nuclear Services -

Rev. 2 Date: Dec. 19,2003

,Card. Variable Name Data Input Type E 1,686 6,116 ESE 11,686 '" 6,116 SE, 1,743. 6,116 SSE 2i094 6,116 12 TAF(K,I) No input required (KOPT(9)=O)

-13 DIST<K,I) No input required (ground level release) 14 HT(K,I) No-input required (groUnd .level release) 1 Represents a coastal sector. The selected distance of 1,381 m represents the distance from the Unit 2 Combined Radwaste/Reactor Building Vent to the, EAB in the SW .and WSW sectors. The SW and WSW

,sectors contain the: minimum distance from the Unit 2 Combined Radwaste/Reactor Building Vent tothe EAB for all land sectors.

Table 5.1-2 Card 91nput K= 1 2 3 45 61 7. 8 9 10 11 12 13.14 15 16 I=1 0 .0 0 0 .0 0 0; 0 0 03 0 0 0 0 0 0 1=2 0 0 0 0 0 0 o o 0 0 o 6 1 0 1 0 1=3 7 1 2 00 0 2 0 0 3 2 0 4. 7 10 25 i=4 44 18 3 1 1 1 .1 3 3. 0 1 1 7 33 63 64

!545 42 14 0 *2 6 4 3 61 01 0 91 34 64 651 j =.643 40 5 0 0 8 16 12 7 .3 1 46 18 29 53 53 11=7 45 28 3 0 0 5 17 11 8 2 1 91 25 19 37 44 1-81,08 70 .5 1 1 5 24 26 3 4 0172 35 36 71 87

1=9 ý85 45 2 0 0 1 191 0 3 0 0 71 21 29 73 80 1=10 9.1, 48 2 0 0 1 9 5 0 0 0 19 46.69147121 1=11 24 21 0 0 0 0 3 1 0 0 0' 36 44141 95 31 1=12 7 0 0 0 0 0 0 0 0 0 0 3 16 34 9 0 l=1 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 P=2 0 0 0 0 .0 1 0 0 0 0 0 0 0 0 .0 0 1=3 6 4 0 1 1 1.1 0 1 2 3 1 0 :3 1 5 6 1=4 11 15 11 1 1 2 5 .4 1 51. 4 5 .21 11 5 1I5 17 19 7 3 0 :6 8 17 13_ 4 0 .9 23 24 6 9 J=2 6 14 16 10 0 1 6 12 15 _16 5 2 27 30, 26 14 12 1=7 17 11 .1 0 1 7:21 18 10 3 0 36 25 11 27 20 1=8 56 37 .6 1 0 3.21 19 10_ 0 4 158 44 36 82 50 V-9 57 45 ;,0 0 0 3 8 6 9 0 1 38 58 36 65 71 1=1.0_39 35. 0 0 0 0 2 1 3_0 0 33 62 84 95 51 1=1-1 15 13. 0 0 0 0 0 0 0 0 0 39 83 83 30 9 1=12 0 '0 0 0 .0 0 0 0 0 0 0 5 16 5 01 0 J=3 1=1 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 P:2 1 :0 0 0 0 0 1 0 1 0 0 0 0 3 1 0 1=3 10 2 1 2 3 2 1 1 2 0 3 3 3 4 11 6 1=4 10 2220.23 4 8 4 4 82 20 5 722 13 Page 13 of 45

ý ZkC,ýl (* - ý ý Calculation No: NMPAST-01-001 Constellation Nuclear Services Rev. 2 Date: Dec. 19, 2003 K- 1 23 4 5 .6 789 10 1112 13 141151.6 1=5 1.8 22 15 7 0 19 17 27 22 7 3 16 42 26 111 9 1=6 11 25 7 0 0 6 16 25 32 8 0 25 .47 32 14 15 1=7 26 1.7 .4 :0 1 7 30 27 36 6 3 33 63 21 43 27 1=8 84 7,1 12 0 1 7' 29 27 21 2 3 69 86 581 84 45 1=9..54 53 61 0 0 1 21 9 17 .3 0 26 80 73 85 57 L=10 38 57 6 0 0 01 20 5 2 0 5_ 69130 84 62 55 1=1_1 I..._20 18 .. 0 0 00 1000 1 62:98 9519 1

_1=12 0 1 0 0 0 0 0 0 0 0 c_9 12 5 1 0 1=4 0 1 0 0 1 1 11 1 1 1 2 0 1 0 2 0 1=2 4 7 9 8 4 4 5 2 6 4 3 6 7 2 ,6 5 1=3 36 49 61 44 45 33 25 35 151.24 23 18 33 5.1 50 40 1=4 84101129 73 51 .83 81 63 61 62 38 61i117 .82 73 60 1=5 651051.81 67,6697134129132108 58 99178 94 70 50 J=4 1=6 9410818.9 37 51 1001.85143199 172 92160181104 81 87 1=7 104 134 1:37 18 4515328911752 16198 4219 17811311127106 I=8 170'356185 12 29 179 5871332 4 121276 229'443 394 300231188 1=9100 34 79 1 3.79 303191,1791.40 140 298 376 232204 11.9 1=10 98161 :29 .0 1 14125 67 45 10 49286387251111.7 62 I=1 1 33 40 1 0 0" 2 1 10 3 0 21952891,39 23 14 1=12 0 0 0 0 0 0 0 0 0 0 20.24 12 .0 0 1=11 b 0 0 0 1 2 1 2 0 1 1 0 0 0 0 2 1=2 8! 68 7 8 5 2:5 6 8 3 3 11 :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 49 33 46 411 37 51 58 95 56 41 39 1=5 27 31 93 ,71 71 63 74 83 52 U48 60102 98 :38 29 1 J 1= 21 33 37 28 38 73 :1t6104106108 97212102 37 12 18 1=7 16 23 24 10 16 762461.7021 3216,139 183 84 22 12 20 1=8 36_ 29 17 4 1.5 767306056114 404,2131349136 52 30 19 1=9 24 18 6 0 0 11235320245 58 621236105 54 21 11 1=1t0 18 23 5 0 1 2 44 62 24 1 71175106 54 7 12

=11 2 6 00 0 0 1 5 1 00 2 656 20 5 1 1=12 10 0 0 0 0 0 0 '0O 0 0 5 4 2 0 .0 J=6.1=1 1 0 0 0 1 1 0 0 2 1 0 1 0 2 0 .0 1=2 4 2 4 9 6 3 0 4 2 3 9 4 2 2 1 5 1=3 13 15 22 26 21 12 i:6 13 14 14 251 28 21 24 25 1:2 1=4 17 19 40 41 30 32 21 18 17 17 30 40 44 34 10 1.5 1=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 71 39 9 8 11 1=7 9 11 41 2 18 45139.52 30 42 85 53 18 3 2 7 1=8 13 7 0 8 24109187158138 93 50 24 15 3 6 1=9 8 7 2 0 0 0 8 25 25 17 1 20 26 9 8 9 1=10 10 "4 0 0 0 0 0 0 0 0 0 17 28 7 5 2 Page 14 of 45

k Constealation i~zr~~-4~b Calculation No: NMPASTO01-001 Nuclear Services. Rev. 2 Date: Dec. 19, 2003 K= 1 2 3 4 15. 7 8 9 1011112113 14115116 1=11 0 0 0 0 0 0 0 0 0 0 0 11 5 i1 0 ,0 i=122 0 0 0 0oo o 0 0 0 0 0 0 0610 1=1 1 I 0 0 3 1 0 41 1 1 1 0 1 1 .0 1 1=2 7 7 8 '101.12 6 8 8 14 5 5 7 14 11 7 4 1=3 21 25 27 33.32 36 23 25 31 28 46 44 33 34 13 26 1= 14 15 36 3'0' 49 38 25 27 31 42 58 62 40 21 12 12 1=5 8 10 3 16 37 30 29 41 26 46 86 81 17 7 3 5 J=7 1=6 5. 2 0 3 21 33 35 "34 40 52 801 54 12 0 1 .3 1=7 1 4 2 2 7 28 29 54 45 47 60 18 5 1 1 2 1=8 10 10 1 0 4 19 361 950 45 '21 14 4 .1 3 7 1=9 14 5 1 0 0 0 3 .2 2 0 0 3 7 1 41 8 1=10 8 901 0 0 .0 0 0 0 0 0 7 8 1 13 6 1=-11 2 0 0 0'0 0 0 0 0 d 0 2 1_ 1 1 0 1=12 0 0 0 000 0 0 0 0 0 01 0 0 0 .0

= Wind 'Speed Category, J = Stability Category, K= wind Direction Table5.2-1 Input References for Similar PAVAN Input Files PAVAN Input File iSimilar PAVAN Input File Unit 1 Turbine-Building.Blowout Panel Unit I ReactorBuilding Blowout. Panel

'Unit 2 Main Steam Tunnel Unit 2 Combined Radwaste and Reactor Building Vent Unit 2 Standby Gas Treatment System Building Unitý2 Combined Radwaste .and Reactor Building Vent ]

,Unit 2 Sampling System Panel Unit 2 Combined Radwaste and Reactor Building Vent[

6. Calculation and Results 6.1. Determination of Distances for Calculations For.stack releases, the maximum ground-level X/Q in a sector may occur at a distance beyond the EAB and LPZ. R.G. 1.145 (Reference 2) recommends making X/Q calculations foreach 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 atboth Units for the following distances (in meters):

100 250 500 510, 525 535 550 600 650 700 750 850 1000 1250 1500 1750 2000 2500 3000 3500 4500 5000 5500 6000 6500 7000 8000 9000 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 LPZ boundaries. All input files, output

.Page 15 of 45

Calculation No: NMPAST-01-001 Constellation Rev.2 Nuclear Services Date:, Dec. 19, 2003 files and other files related to the testcases 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, 0.5% X/Qs for non-coastal sectors were visually checked in each. PAVAN output file. Twenty-eight cases were hand-checked where the 0.5%X/Q was not bounded or near neighboring points. These cases included:

Unit 1,Main -Stack to EAB - SSW Sector

Unit 1 Main Stack to EAB -E Sector

Unit 1 Main Stack to EAB - ESE Sector

Unit, I Main Stack to EAB - SE Sector

° Unit. I Main Stack to LPZ - SW Sector

Unit 1 Main Stack to LPZ - WSW Sector

Unit 1 Main Stack to LPZ - E Sector

Unit I Main Stack to LPZ - ESE Sector

UnitI Reactor Building Blowout Panel to EAB - SW Sector

Unit 1 Reactor Building Blowout Panel to EAB - WSW Sector

Unit 1 Reactor Building Blowout Panel to EAB - E Sector

Unit. I Reactor Building Blowout Panel to LPZ - SSW Sector

Unit 1 Reactor Building Blowout Panel to LPZ - SW Sector

Unit I 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

- Unit 2 Main Stack to LPZ - SW Sector Unit, 2 Main Stack to LPZ - WSW Sector

Unit 2 Main. Stack to LPZ - ESE Sector

Unit2 Main Stack to LPZ - SE Sector

Unit 2 Main Stack to LPZ - SSE Sector

Unit 2 Combined Radwaste/Reactor Building Vent to EAB - SW Sector

Unit 2 Combined Radwaste/Reactor Building Vent to EAB - WSW Sector

Unit.2' Combined Radwaste/Reactor Building Vent to EAB - SSE Sector

Unit'2 Combined Radwaste/Reactor Building Vent to LPZ.- SSW Sector

Unit 2 Combined Radwaste/Reactor Buildi ng Vent to LPZ - SW Sector

Unit 2 Combined Radwaste/Reactor Building Vent to LPZ - SE Sector

Unit,2 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 XIQ frequency values extracted from the PAVAN output files. These values represent Page 16 of 45

a o nste latio Calculation No:INMPA ST-01 -001 nRev.2 Nuclear Services Date: Dec. 19, 2003 the.0 -. 2hour X/Qs for the sector. It was determined that all the 0.5% XIQ values were

calculated cor.rectly by PAVAN, and are therefore valid. Hence, the PAVAN output values were extracted and required no additional processing. These calculations are included in the 0.5%"Sector Dependent,Calculationstfolderon the attached disc.

6.31 ENVLOP Error According to'the PAVAN user's guide (Reference 8), 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 X/Q value which is equaled or exceeded 5.0% of the time was not obtained in six of.the PAVAN calculation runs. The six runs included:

" Unit 1 Main Stack to EAB

" Unit 1 Main Stack to 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. EAR 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 ordered X/Qfrequency values extracted from the PAVAN..outpu.t files. These values represent the 0 - 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months overall site X/Qs. In addition, the intermediate time-period overall site

X/Qs were manually calculated using the PAVAN algorithm coded into ExcelS spreadsheet form. Intermediate time points.of 8,1 6, 72 and 624 were utilized in this spreadsheet algorithmi which is8replicated from the PAVAN algorithm. These manual calculations were. performed.

,using the methodology as described in R.,G. 1.145 (Reference 2) and the PAVAN user's guide (Reference 8). These calculations are included in the `5% Site Limit Calculationsfolder on the enclosed CD.

6.4.. Results Results of PAVAN calculations are included in Tables 6.4-1 through 6.4-5. The actual PAVAN outputfiles are included in the Output Files folder on the enclosed CD. Table 6,4-1 lists the 0.5%6/.sector dependent 0- 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (non-fumigation) XIQs along with .thefumigation 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 XIQs for non-coastal sectors.

Page 17 of 45

.2-1cof.-O Calculation No: NMPASTI01-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19,2003 Fiqure 6.1-1 Unit I Main StackXiQ Versus Distance 5.50E-06 OE&06 4-OOE-06.

S3.50E-06 3.OOE-06 2,50& 06 1,ODE-06 5.000 -w distance (in)

Page 18 of 45

Z-k C47(*-(ýý VA Calculation No: NMPAST-01-001Rev.

Constellation 2 Nuclear Services Date: Dec. 19,,2003 Figure 6.1-2 Unit 2 Main Stack X/Q, Versus Distance 3.50E-06 3.OSE-O8 2.50E-06 E

S2.00&-06 1.50E-06 I .OE-06 5.(OE-07 distance (m)

Table 6+4-1 Nine Mile Point 0.5% Sector DePendent Short-Term X/Qs Calculated with PAVAN Source Sector Non-Fumnigation Fumigation EAB Non-Fumigation Fumigation LPZ 0-2 Hour EABX/Q XIQ (seclm 3) 0,2 Hour LPZ.X/Q 3 X/Q (seclm3)

(sec/m )

(secim3) +

-1 1 I + -~------"-------

Unit 1 Sý 3,78,E-06 3,28E-05 2.87E-06 2.12E-05 Main SSW 2..E-6 3.65E-05 2.22E-06 1.1 55E-05 Stack SW 3-46E-06 4.62E-05' '2.66E-06' 1.55E&05 WSW 1.55E-06 5.98E-05 j 1.25 E-06' 9.85E-06 E, 2;57E706 1 3.09E-ý05 2.05E-06 1 1.34E-05, ESE 2.60E-06' 3:13E-05 j 2.06E-06 1 1.41 E-05 1 1.67E-06 1.24E705 SE 2.21 ýE-06 2.59E-05 SSE. 2.18E-06 2 96E-05 1.61 E-06 1.32E-05 Unit 2 S: 2.,19E-06 2.36E-05 1-73E-06' 1.42E-05

.Main SSW 1.792-06 1 2.51 E-05 1._I49E-06 - 1.15E-05 Stack SW 1.97E;-06 2.90E-05 1.76E-01' 1.1 E-05 WSW 8.82 E-07 2.68E-05 7.80E-07' 6.04E-06 E 1.64E&06 2.93E-05 I A3E-06 1.02E-05, ESE 1.69E-08 2.96E-05 1.2BE-06' 1.06E-05 SE I.4-628E0 1,66&E-06 1- 9.66E-06 SSE 1.31 E-06 2.25E&05 1.04E-06' 1.01 E-05 1 Value manually verified in accordance with Section 6.2.

Page 19 of 45

t4l.tl CkIG4 ý Calculation No: NMPAST-O1-001 constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003 Table 6.4-2 Unit I Main Stack Non-Fumigation ..... XIQ X/ QValues (sec/mj)

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 1.12E706 4.65-071 1.31E-07 2.80E-08 SSW, 2.98E-06 1.36E-06 9.21 E-07 3.94E-07 1.16E-07 2.62E-08 SW, ;346E-06 1.35E-06 8.40E-07 3.02E-07 6.93E-08 1*.15E-08 WSW 1.;55E-06 4.75E-07 2.63E-07 7.30E-08 1.16E-08 1:22E-09 EAB El 2:572-06 1.29E-06 9.10 E-07 4.30E-07 1.46E-07 3.92E-08 ESE' '60E-06 1.24E-06 8.62E-07 3.88E-07 1.23E-07 3.03E-08 SE' 2.21E-06 1.06E-06 7.36E-07 3.322E-07 1.06E-07 2.61E-08

,SSE 2.18E-06 I.01E-06 6.89E-07 2..99E-07 9.02E-08 2108E-08 OverallSite 2 2.61E-06 130E&06 9.22Er07 4.34E-07 1.47E-07 3.92E-08 S 287E-06 1.26E-06 8.40 E-07 3.45E-07 9.62E-08 2.02E-8 SSW 2.22E-06 1 03E-06 6.96 Eý07 3.01E-07 9.01 E-08 2M06E-08 SW1 2.66E-06 1.21E-06 8.13E-07 3.45E-07 1.01E-07 2.24E-08 WSW, 1.25E-06 5.22E-07 3.38 E-07 1.31E-07 3.37E-08 6.41 E-09 LPZ E! 2.05E-06 1,01E-06 7.12 E-07 3,32E-07 I.i1E-07 2.89E-08 ESE' 2.06&-06 9.59E-07 6.54E-07 2.85E-07 8.66E-08 2.01 E-08 SE 1.67E-06 7.68E-07 5.20E-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 SiteI 1.90E-06 9.53E-07 ,6.74E-07 3.18E-07 1.08E-07 2.89E708 1 With the exception of Annual Average,;al1 values were verified in accordancewith Section.6.2.

2 With the exception of Annual Average, all values were calculated in accordance with Section

_6.3.

Table 6,A43 Unit I Reactor Building Blowout Panel X/Q Values X/Q (sedm')

Distance. Sector 0-2 0-8 8-24 1-4 4-30 Annual Hours Hoursý Hours Days Days Average S 4.59E-05 2.48E-05 1.83E-05 9.39E-06 3.61E-06 1.12E-06 SSW 6.34E-05 3.722-05 2184ý-05' 1.59ý-05 6.93E-06. 2M50E-06 SW' 1.02E-04 6.21 E-05 4.84E705 2.81E-05 1.29E-005 4.90E-06 WSW1 1.58E204 9;48E-05 7:35E-05 4.24E-05 1.92E-05 7.29E-06 EAB El .7.42E-05 4.26E-05 3.22 E:-05 1.76E-05 7.43E-06 2,58E-'06 ESE .5.44E-05 3.082-05 2;32 E-05 1.25&-05 5.14E-06 1.73E-06 SE .2.97E-05 1.62E-05 1.20E-05 6.21 E-06 2.41E-06 7.60E-07 SSE 4.11E-05 2.23E-05 1.64E-05 8.43E-06 3.24E-06 1.01 E-06 Overall Site: 1.90E-04 1.28E-04 1.05E-04 6.80E-05 3.67E-05 1.72E-05 LPZ S 1.31Ew05 5.96E-06 4.03E-06 1.72E-06 5.05E-07 1. 13E-07 SSWI 1.33E-05 6.17E-06 4.202E-06 1.82E-06 5.51E-07 1.27E-07 8w, 1,81E-05 8.19E-06 5.52E-06 2.34E-06 6.82E-07 1.51 E-07 Page 20 of 45

Calculation No:: NMPAST-01-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003

.X/Q (sec/m)

Distance. Sector 0-2 0-8 8-24 1-4 4-30 Annual Hours Hours HOurs Days Days Average WSW 2.07E-05 8.9E,-06 5.93E-06 2.40E-06 6.57E-07 1.342&07 E 2.315-05 1.08E-05 7.35E-06 3.21E-06 9.80E-07 2.29E-07 ESE 1.59E-05 7.402-06 5.05E2-6 2.20E-06 6.68E-07 1.55E-07 SE1 9.24E-06 438E-06 :3.01E-06 1.34E-06 4.19E-07 1.015-07 SSE' 1.10E-05 5.09E-06 3.45E-06 1.49E-06 4.46&-07 1.02E-07 Overall Site 3I58E-05 1.3E-05 1.10&05 4.675-06 1.37E-06 3.04E-07 1 With theexception 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 6.4-4 Unit 2 Main Stack Non- Fumigation X/Q Values X/Q(sec/m3 )

Distance Sector 0-2 0-8 8-24 1-4 4-30 Annual Hours Hours Hours Days D.

. ays Average S 2.19E-06 9.705-07 6.45E-07 2.67E-07 7,49E-08 I.59E-08 SSW 1.79E-06 8. IOE-07 5.46E-07 2.31 E707 6.7.5E-08 1.505-08 SW 1.97E-06 7.71 E-07 4.83E-07 1.75E-07 4.06E 08 6.80E-09 WSW 8.82E-07 3.01E-07 1.76E-07 5.50E-08 1.032-08 1.33E-09 EAB E 1.64E-06 7.81E-07 5,40E-07 2.42E-07 7.642-08. i.87E-08 ESE 1.69E-06 7.84E-07 5.34E-017 2.32E-07 7.02E-08 1.63E-08

.SE 1.44E-06 6.86E-07 4.73E-07 2AIE-07 6.65E-08 1.62E-08 SSE 1.31E-06 6.05E-07 4.11E-07 1.77E-07 5.29E-08 1.21E-08 OverallSite_ _ 1.56E-06 7.53E-07 5.225-07 2.36E-07 7.548-08 1.87E-08 S' 1.73E-06 7.79E-07 5.22E-07 2.20E-07 6.33E-08 1.38&-08 SSW 1;49E-06 6.94E-07 4.75E-07 2.082-07 6.35E-08 1.49E-08 SW1 1.,75E-06 8.01 E-07 .5.41 E-07 2.31 E-07 .6.82E-08 1.53E-08 WSW, 7.80E-07 325E-07 2.09E-07 8.092-08 2.06E-08 3.88E-09 LPZ E 1.43E-06 7.05E-07 4.95E-07 '2;30E-07 7.655-08 1.99E&08 ESE' 1.28E-06 6.08E-07 4.19E-07 1.87&-07 5.85E-08, 1.41 E-08 SE' 1.06E-06 4.982-07 3.41 E-07 1.50E-07 4.62E-08 1.09E-08 SSE1 1.04E-06 4.76E-07 3.22E-07 i.37E-07 4.06E-08 9.13E-09 Overall Site' .1.20E-06 6.1 02-07 4.342&07 2.08E-07 7.242-08 1.99E-08 1 With the exception 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 63.

Page,21 of 45

Calculation'No: NMPAST-01-001

@ Constellation Rev. 2 Nuclear Services Date: Dec. 19,.2003 Table 6.4.5 Unit 2 Combined RadwastelReactor Building Vent X/Q Values X/Q (sec/mj)

Distance, Sector 0-2 0-8 8-24 1-4 4-30 Annual Hours Hours. Hours Days Days Averagce S 4.65E-05 2.5, E-05 1,85&-05 9A46E-06 3.62E&06 1.12E-06 SSW 5.47E-05 3.10E-05 2.34E-05 1,27E-05 5.25E-06 1.79E-06

sw 8.75E-05 5.12E-05 3.91 E-05 2.18E 05 9.46E-06 3.40E-06 WSW, 9.14E-05 5.1-05 3.85E705 2.06E-05 8.382-06 2.79E-06 EAB E 8.00E-05 4.70E-05 3.60E-05 2.03E-05 8.85E:-06 3.22E-06 ESE 6:22E-05 3.57E-05 2.70E-05 1.48E-05 6.23E-06 2.16E-06 SE 4.07E-05 2.32E-05 1.75E-05 9.54E306 .98&-06 1.36E-06 "SSE' 3.85E-05 2.05E-05 1.50E-05 7..56E-06 2.84E-06 8.54E-07.

Overall Site 2 1.19E-04 7.372-05 5.80E-05 3.45E-05 1.64E-05 6.56E-06 S 1.30E-05 5.90E-06 3.98E-06 1.69E-06 4.92E-07 1_09&-07 SSW, 1,32E-05 6.11E-06 4.15E-06 1.79E-06 :5,37E-07 1.232-07 SW' 1.01E-05 8.15E-06 5.47E-06 2_30E-06 6.66E-07 1.46E-07 WSW 2.07E-05 8.92E-06 5.86E-06 2-36E-06 837E-07 1.29E-07 LPZ E 2.31E-05 1.07E-05 7.28E-06 3.136E-06 9.56E-07 2.21E-07 ESE 1.58E-.05 7.32E-06 4.98-06. 2A16E-06 6-50E-07 1.50E-07 SE 9.,24E-06 4.36E-06 2.99E-06 1.32E-06 4.11 E-07 9.80E-08 SSE' 1.10E-05 5.06E206 3.42E-06 1.47E-06 4.35E-07 9.83E-08 Overall Site 3.58E-05 1.62E-05 1.09E-05 4.59E-06 1.33&-06 2.93&-07 i With the exception of Annual Average, all values were verified in accordancewith Section 6.2.

2 :With the exception of Annual Average, all Values were calculated inaccordance with Section

7. Conclusions Tables 7-1 and 7-2 provide conservative atmospheric dispersion coefficients (XiQs) to .be used to perform calculations to assess radiation exposure -atthe EAB .and. LPZ due to: postulated accidents occurring at NMP. Unit 1 and Unit 2. Ground-level releases include releases from

.the Unit 1.Reactor Building Blowout Panel, Unit 1 Turbine Building Blowout Panel,:Unit 2 Combined Radwaste/Reactor Building Vent .Unit 2 Main Steam Tunnel, Unit 2 Standby Gas Treatment System Building and Unit 2 Post Accident Sampling System Panel. Elevated releases include releases from the Unit 1 Main Stack and Unit 2 Main Stack.

For the EAB, 0 -2 hour X/Qs 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 XiQs for each time interval. Fumigation X/Qs are considered for elevated releases only and are, conservatively assumed to exist for 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

Constellation Calculation No: NMPAST-01-001 Rev. 2 Nuclear Services Date: Dec.. 19, 2003 Table 7.1 Ground-Level Release X/Qs Selected for Evaluation at NMP

_________XIQ (sec/rn 3 Unit Boundary 0.-2 0-8 8-24 1-4 4-30 Hours Hours Hours Days 4

1 IB 1.90&W4 3 LE 1.63E-05 I IOE-05 4.67E-06 ' 1.37E-06 2 EAB' 1.1 9E-04 34

-PZ

. . 33E,06

... .1..............

2P. 1.62E-053 1.09E-053 4.59E-06 I1.33E-063 1 0-2 Hour X/Qs at the EAB are conservatively assumed to exist for.the duration 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; 3 Overall Site X/Q Value:

Table: 7-2'ElevatedRelease X/Q Selected for Evaluation at NMP

....... _ X/Q (sec/mr )

Unit Boundary 0-2 0-8 8-24 1-4 4-30 SHours Hours Hours Days Days 2PZ_ 2j.1.42E-05 8.40E-07 23.45E-07 1.11 E-078

=.96E-0,5 2 51 2# 1.42EM-05 5.41 E707' 231E 07' 7.65E-08" I 0-2, Hour X/Os at.te EA_3 are conservatively assuniea to. exist for tne* duraton or 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 assumed to exist for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the accident.

3 WSW sector short-term fumigation value.

4 ESE sector short-term fumigation value.

5 S sector short-term fumigation value.

6 S sector X/Q value.

7 SW sector.X/Q value.

8 E sector XkQ value.

Page 23 of 45

Calculationi No: NMPAST-01-001 Rev. 2, K'ý1ýConstellation Rv2 Nuclear Services Date:, Dec. 19, 2003

8. References.

1. CNS Quality Assurance Program, Rev. 4, Doecember 1, 2002..

2. Regulatory Guide 1.145, Rev. 1, 'Atmospheric 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 Dispersionh of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",

July 1977.

4. NIMP Purchase Order No. 02-40502, May 22, 2002.

5ý. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents atNuclear Power Reactors", July 2000.

6. 10 CFR Part 100, "Reactor Site Criteria", December 1996.

7. 10 CFR. Part 50, "Domestic:Licensing of Production and Utilization Facilities", August 1991.

8. NUREG/CR-2858, "PAVAN: An Atrmospheric Dispersion Program for Evaluating Design Basis Accidental Releases-of Radioactive Materials from Nuclear Power Stations",

November 1982,

9. 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.

1 0.:Meteorological Evaluation Services, Inc. "Accident X/Q Values for Nine.Mile Point unit I Releases from the Main Stack and the Reactor and Turbine Build ings', August 7, 1990.

11. 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.

12. NMP Drawing C-26658-C, Rev. 4, July 1974.

13.NMP Unit.12 USAR.Figures 2.3-43 through 2.3-46,.Amendment 3, .June 1983.

14.NMP Unit 2 USAR Section 2.3.4.4.2, Rev. 10, November'1998.

115. CNS PAVAN Computer Code Verification, Rev. 1, June 24, 2002.

16. NMP Drawing C-18713-C, Rev. 9, May 1_974.

17. NMP Unit 2 USAR Figure 1.2-11, Rev. 0, April 1989.

18. Teleconference with NMP (Ted Kulczycky, Al 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 QNS-03-21. "Comments on NISYS Review of CNS Calculations NMPAST-01-001 and NMPAST-02-001,"-Shane R. Gardner, September 24, 2003.

21.Regulatory Guide 1.23, "Onsite Meteorological Programs," February, 1972.

Page 24 of 45

4 zt-C 0:1,6 - CVý Calculation No: NMPAST-1-00!1 Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003 Appendices AppendixA - Figures: EAB and LPZ Regions Showing. Associated XQ Directions Appendix B - PAVAN Output Apperdix C - Listing of. Files on DATA, CD-ROM for.Calculation NMPAST-01 -001 Page 25 of 45

.31 Calculation No: NMPAST-01-401 Constellation Rev. 2 Nuclear Services Date: Dec. 19,2003 Appendix, A- Figures: EAB and, LPZ Regions Showing Associated X/Q Directions Page 26 of 45

.Calculation No: NMPAST-01-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003 Figure A-I EAB and Associated X/Q Directions r * .NNW

. ........ N........ _NNE',

N I - ,, - ,

~'4**,w*Uu I II*tI ,*,, 1 '1 NE.

A I

Ii I

NWSW:I#,MOrvO 1~

8 S stmIs~

Page 27 of 45

.33, 1ýzi c47 41 Calculateion No- NMPAST-01-001 Constellation Rev. 2 Nuclear Services Date: Dec. 19. 2003 Figure A-2 LPZ and Associated XIQ Directions NNW N

--:-_NNE WNWW

.r f fOKm-(a2

'7 NE 1).E) ENE

,019MILE POI~t.2 STA.CK I

GKNI (3. IiALE) LOW POPUJLATION ZQFIIL ObJWDARY

$CALL- MILI3 0.

SCAL.E -KL0NIVETR Page :28 of 45

Calculation No: NMPAST-01-00134 Revw. 2 constelatnion Date: Dec. 19, 2003 Nuclear Services Appendix B - PAVAN Output Page 29 of 45

Constellatio Nuclear Services Calcutation.No:NMPAST-01-0O1 Rev. 2 Date: Dec. 19, 2003 IUSNRC COMPUTER CODE-PAVAIN, VERSION 2.0 RUN DATE: 09-03-02

/PLANT. NAME.: NINE MILE POINT METEOROLOGICAL INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/02 WIND SENSORS HEIGHT: 60.7 METER TYPE. OF RELEASE: ELEVATED 106.7 METER DsLTA-T HEIGHTS: 51.2 METER:

SOURCE OF DATA: JOINT FREQUENCY DISTRIBUTION REPORT (JFD) NINE MILE PCINT NUCLEAR STATION COMMENTS: NINE MILE POINT UNIT :1 MAIN STACK 0; EkA/LPZ PROORAM: PAVAN, 10/76, 8179 REVISION, IMPLEMENTATIION OPREGULATORY GUIDE 1.145 0 RELATIVE CONCENTRATION (X/Q) VALUES (SEC/CUBIC METER)

VERSUS HOURS PER YEAR MAX AVERAGING:TIME 3-2 HR X/Q IS

.DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR (METERS) 0-2, HOURS 0-8 HOURS 8-24 HOURS 1-4 DAYS 4-30 DAYS ANNUAI AVERAGE -N SECTOR SECTOR S 2000. 3.78E-05 1.68E-06 1.12E-06ý 4.658E-07: 1.312-07 2.80E-08 437 sS SSW 2.98E-0S 1.36E-06 9.218-07, 3.94E-07 1.16E-07 2.62E-08 22.3 SSW 8.402E-07 35'2 1200. 3.46E-06 4 .35E-07 3.02E-0,7' 6.93E-03 1.15E-08 sw 1.168-03 1.:22E-09 5.9 WSW .830. 1.55E-06 2.63E-67 7.30E-08 WSW 1 ;4-3E: 05 1 .048-03 1.07E-09 6.3 w 830. 4.36E-07 2.41E-07 '6,62E-08 WNW 830.

1. 72Eo6 6.46E-07 3.9*68-0o7 1.37E-07 2-982E-Ca 4.61E8:09 4.5 WNW 1.83E-06 NW 830. 7.72E-07 S.02E-07 1.97E-07 5..15E-03. 9.968-09 5.8 KW 7,79E-07 9.748-09 6.5 NNW NNW :830. 1. 85E -06 5.05t-07 1. 97E- 07: 5.09E-08, .-3 N 830. 1.77E-06 7.31E-07 4.6.-o07 1.79E-07 4.51E-03 ý8.34E-09 5.6 N NNE 830. 1. 56E- 06 S.73E-07 3.,47E-07 1.17E-07 2.44E-03 3.60E-09 5.5 NNE NE .830., 1.38E-06 4.S6E-07 .2.62E-07 'v.85-08 1.39E-03 1.682-09 5.1 NE 6.792g-07 5.4 ENE n3o. 2. oIE- 06 9.76E- 07 13..09E-0.7 9..99E-03 ,2,51E-08 ENE -0 E

igoo. 2.57E-06 1 .29E-06 9.10E-07 1,46E-07 3.92E-08 I17.5 E

.3,88E-07 i.23E-07 3,. 03E-08 16.1 ESE g1900. 2.60E-06 I.:24E-06 ,8.62E-07 SE 2300, 2.2 18-06 1.06E-06 7.36E-07 1ý.-32807 1. 06E-07 2ý.618-08 14.8 SE SSE 2000. 1.01E-06 6.89E-07 2.99E-07 9.02E7O-0: 2:.08E-08 13.5 SSE MAX X/Q 3.18E-06 TOTAL HOURS AEROUND SITE: 2130.

S20 2.3.4 830.1 4..628-06 2.*17E-06 1.468-06 6.16E-07 1.78E-07 3.92E808 SITE LIMIT o.COE+00 0.00E-00 0.00E+00 0.00E+00 0,.00800 3,92E-08 00.5 92CERNT X/Q-TO AN INDIVIDUAL IS LIMITING.

0X/Q-VALUES (SEC/CUBIC METER) FOR FUMIGATION AT THE BOUNDARY:

DOTlIWIND DISTANCE FUMIGATION:

SECTOR (METERS) X//

s 20.00. :31.288e-05 SSW 1500. 3.85E-05 SW 1200. 4.62E-05 WSW 830o. 5.988E-C5 W 830. 5.,98E-05 WNW 830., 5.98E-05 NW 830. 5.98E-05 NNW 830., 5-98E-05 N 830. 5.98E-05 NNE 830. 5.98E-05 NE 830, 6.008-05i ENE 830. 6.03E-05 Lp s 1900o. 3-692-05 ESE 1900. 31.13Z-05 Page 30 of 45

9 )

a.

.4-0 cl) ca MU en0 000 oz

0) V)

Calculation No; NMPAST-01-001 Rev; 2 Nuclear SerV'ice Date: Dec. 19, 2003 1USNRC COMPUTER CODE-PAVAV, VERSION 2.0 RUN DATE: 09-03-02

/PLANT NAME: NINE MILE POINT METEOROLOGICAL'INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT: 60.7 *METER TYPE OF:RELEASE: ELEVATED 10E.7 METER DELTA-7 HEIGHTS: S1.2 METER SOURCE OF DATA: JOINT FREQUENCY DISTRIBUTION REPORT7 ý(JFD) MILE POINT NUCLEAR STATION" M.NINE

,COMMENTS: NINE.. MILE POINT UNIT :1 MAIN STACK TO EAB/LPZ PRCGRAM: PAVAN, 10/76, 8/7,9: REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145 0: RELATIVE CONCENTRATION I(X/Q) VALUES (SEC/CUBIC METER)

VERSUS HOURS PER YEAR MAX AVERAGING TIME 0-2 R ,X/'Q Is DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR. (METERS) 0-2 HOURS 0-8 HOURS 8-24 HOURS 1-4 CAYS 4-30 DAYS: ANNUAL AVERAGE N .SECTOR SECTOR S 6116. 2.87E-06 ".266-06 8.40k-07 3.45E-07 9.62E-08 2.02*-08, 43, s.:

SSW 6116. 2.22E-06 1.03E-06 6.962-07 3.01E-07 9.ClE-08 2'.06E-08 23.8 SSW SW 6116. 2.66E-06 1.21--0,6 8..,132-07 3."4 5E-'07 1.C1E-07 -2.24E-08 35.4 SW WsSW 6116. 1.25E-06 5,22E-07 3.382-'07 1.-3 1E-07 3 .37E-08' 6.41E-09 4.7 WSW W 6116.. 1.14E-06 4 .,84E-07 3.15E-07 ; .24E-07 3.25E-08 6.-31E-059 5., W WNW 6ý116. 1.23E-06 5.53E607' 3.72E-07 1.576-07 4- S4E- 08 9.96E-09 6_9 WiSH NW 6116. 1.20E-06 6,5E-07 4.29E-07 2.04E-07 6 .98E-08 1.88E-08 .5.7 NW NNW 6116. 1.23E-06 5.99E-07 471:7E-07 1.90E-07 6.16E-08, 1. 55E08 6.9 NNW N 6116 1.1 - 05' 5 481E-07 3.86E-07 1.80E-07 6. 00E-.08 1.576E-08 4.3 N NNE 6116 1.13E-06 5.366-07 3.69E607 1.638-07 5.09t-08 1.22E-08 5.3 NNE NE 6116. 1.08E-06 5.01E-07 3.42E-67 1.496-07 4.5E-08 1.06E-08 6.6 HE ENE ,'116.. 1.37E-06 6.83E-07 4.,83_607 2.28E-07 7,74E-08 2.07E-081 6.8 ENE E 6116. 2.OSE-06 1.01E-06 7 .12E-.07 3.32E-07 1.. 11E-07 2.89E-08:. 18.4 E ESE 6116. 2.06E-06 959E-07 6.54E.07 2.-85E-0.7 8.f6E-08 2.01E-08 20.5 ESE SE 6116. 1.67E-06 7.68E-07 S.,.206E-0.7 2.:23E-07 6.63E-08 .S OEE08- 14.2 SE SSE 6116.. 1.61E-06. 7,25E607 4.86E-07 2.046-07 5.68E-08 1.28E-08 15.1 SSE MAX X/Q 2.87E-06 TOTAL HOURS AROUND SITE: 223.7 SRP. 2.3.4 6116. 3.89E-C6 1.73E-06 1I,5E-06 4.79E-07 1.'35E-07 2.89E-08 SITE LIMIT 0.00E+c0. ,00E+00, 0.00E+00 0.00E+00, 0.00E+00 2.89E-08 00.5 PERCENT X9Q TO AN INDIVIDUAL IS LIMITING.

OX/Q VALUES (SECiCUBIC METER) FOR FUMIGATION AT THE BOUNDARY:

DOWNWIND DISTANCE FUMIGATION SECTOR (METERS) X/D S 5116: 2,129-05 SSW 6116, 1.559-05 SW 6116. 1.55E-05 WSW 6116. 9,856E06 W 6116. 9.856-06 WNW. 6116, 9.85E-06 NW 6116. 9.85E-06 lNW 6116. 9.855-06 N 6116, 9:."856-06 N IE 6116. 9.85E-06 NE 6116. 1.01E-05 ENE 6116. 1.04E-05 E 6116. 1.34E-05 ESE 6116. 11.41E-05 Page 32 of 45

Constellation Calculation No: NMPAST-01-001 Rev, Nuclear Services 2 Date: Dec.. 19, 2003 SE 6116. 1.24E-05 SE 6116. 1'.32E-05 OD Page 3.3 of 45

Constellation Calculation No. NMPAST-01-001 Rev. 2

\ Nuclear Services Date: Dec. 19,2003 1USNRC COMPUTER CODE-PAVAN, VERSION 2.0 RUN DATE: 09-:03-02

/PLANT NAME: NINE MILE POINT METEOROLOGICAL INSTRUMENTAT]ON DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT: 60.7 METER TYPE OF RELEASE; GROUND LEVEL RELEASE DELTA-,T HEIGHTS: S1.2 METER SOURCE OF DATA: JOINT FREQUENCY DISTRIBUTION REPORT (JFD) NINE MILE. POINT NUCLEAR STATION COMMENTS: WINE MILE POINT UN IT REACTOR BUILDING BLOWOUT PANEL TD EAB/LPZ PROGRAM: PAVAN, 10/76, 8/79. REVISION., IMPLEMENTATION oF REGULATORY GUIDE1...145 0 RELATIVE CONCENTRATION (X/Q) VALUES (SEC/dUBIC METER)

VERSUS ROURS PER YEAR MAX AVERAGING TIME 0-2 HR.X/Q IS DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR, (METERS), 0-2 HOURS 0-,8 HOURS. 8-24 HOURS 1-4 DAYS 4-30 DAYS ANNUAL AVERAGE IN SECTOR SECTOR 2000. 4.59tE-0S 2,48E-05. 1.83E-C5 9.39E=06 3 .618- 06 *1.12E- 06: 4.3 s S SSW 1500, 6.34E-05 3 .72E-05 2.84E-C5 I.59E-05 6.93E-06 2.50E-06 6.8 SW 1200, 1.02E-04 6.21E-05 2.8I-O05 1.29E-05 4.992wO0 12.,,5 WSW SW

.WSW 830. 1.58E-04 R9.4 8E-05 7 .35E-C5 4. 24E-:Os 1. 92E-05 7.29E-06 .28. b WSW fJ W 830. 1. 87E-04 1. 13E-04. 8.77E.-C5 5.075E-05 2.30E-05 8.78E-06 32.8 Nw WNW 830, 1 .835- 04 1. 12E-04 8.78E-05 5.16E-os 2.40E-05 9.44E-06 28.4 .W N-W $30. 1. 71E-04, 1..13E-04 9.15E-05 5.83E-os 3.05E-05 1.38E-OS .23.0 NW HNW 1.06E-04 6. 63E-05 3.40E-05 .50OE-05 27.3 NNW N

830.

830,

.2.OIE-04 1.31E-04

.1. 3SE-04 1. 088E-04 6.6-5Eo05 3.33E-,5 1.43E-05

-Z1

2. 1E-04 365 NNE NNE 83.0 1 5E- 04 1.23E-04, 9..76E-05 5.92E-05 2.898-05 .1.20E-05 28.7 NNE 0~~

NE 830. 2.3'4E 9.4 ,1. 4E0 1.15E-04 6 . 89E-05 7.51E-05 3..3OE-CS 1.34E-os 43.7 ENE ENE 830: 2.26E-04 1. 4aE-04 1.19E-04 3.872E-CS 1.72E-0s 41.0 E E 1900: 7.42E-05 4.26E-05 3.22E-65 1. 76E-05 7.43E-C6 2.58E-06 7.3 ESE 1900. 5 .44E- 05 3.08E-05 2.32E-05 1,25E-05 5..14E-C6 1.73E-,06 .6.9 ESE SE 230.0. 2.97E-05 1.62E-05 1.20E-05 8.43-06 6 -21E- 06 2.41E-C6 7.60E-07 '2.7ý SE SSE 2000. 2. 38E- 05 2 .23E-OS, 1.64E-05 3. 43E- 04 3. 24E-'06 i.. 01E-06' A.4-4 SSE 2.34E-004, TOTAL HOURS AROUND SITE:

MAX X/Q .334..4 SRP. 2.3..4 830. 4.44E-04 2.S98-04 1 .98E-04. 4.,78E-00 1.72E-05 SITE LIMIT 0.o08oo00 o.ooEo00 .0.OOE+/-o0. 3. 00E+00 0.008+/--00 1.72E-05 00.5 PERCENT X/6 TO AN INDIVIDUAL.IS LIM4ITINlG-(AJ Page 34 of 45.

Calculation No; NMPAST-01-001 Constellation Rev. 2 NuclearCServices Date: Dec. 19, 2003 1USIMC COMPUTER, CODE-PAvANe, VERSION 2.'0 RUN DATE: 09-03-02

/PLANT VAME NINIE MILE POINT METEOROLOGICAL INSTRUMENTATION DATA.PERIODM 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT: 60.7 METERý TYPE OF RELEASE: OROUND LEVEL RELEASE DELTA-T-HEIGHTS: 51.2 METER.

SOURCE OF:DATA':. JOiNT FREQUSNCY DISTRIBUTION REPORT (JFD).NINE.MI LE POINT NUCLEAR .STATION COMMENTS:: NINE MILE POINT UNIT 1 REACTOR BUILDING BLOWOUT PANEL TO EAB/LPZ PROGRAM: PAVAN, 10/6.., 8/79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.S45 0 RELATIVE CONCENTRATION (XjQ) VALUES (SEC/CUBIC METER)

VERSUS HOURS PER YEAR MAX AVERAGING TIME 0ý-2 HR X/Q IS DOWN'WIND DISTANCE. EXCEEDED, DOWNWIND SECTOR (METERS) 0-2 HOURS 0-8 HOURS 8-24 HOURS, 1-4 DAYS 4-30 DAYS ANNUAL AVERAGE IN SECTOR. SECTOR S 6116. 1. 31E-05 5.96E-06 4. 03E-06 1. 72E-06 5.05E 07 1. 132-07 14.3 SSW 6116. 4.20E-06 1. 82E-06 5.51E'-07 1.27E-07 SSW 1.33E-05 6,17E-06 39ý2. 7 Sw 6116. '8.192-06 5. 522-06 2.34E-06 6 *82E- 7 1.51E-07 19.7 SW 1.B1E-0 '5 8.99E-06 WSW WSw 6116, 2. 07E-05 5,. 93E-06 2.40EA06 6 .57EB07 1.34E-07 24.1. W WNW W 6116.

6116.

2.74E-05 2.76E-05 1.18E-05

.1.19E-05

- 770E-06ý

7. 3 1E06, 3 ,08E-06 3.13E-06 8.272-07 1.65E-07 1.70E-07 30.11 26..4 WNW NW e

7:.,96E-06; 1 .03E06 2.36E 07 20.5.

NW NNW 6116.

6116.

2 .54E-05 2.92E-05 1'. 17E-05 1.35E-05 9.12E-06 3.44E-06' 3.93&-06 1.17E-06 2.67E-07 23.L NNW N

-a N 6116. 2. 78E-05 1 28.-05 3.73E-06 1-.IE206 2,53E-07 21.7 NNE 6116. 3.03E-05 1.343-05 8.89E-06 3.66E-06' 1.03E-06 2.16E-07 .27.9 NNE NE 6116. 3.85E-05 1.68E-05 1 .D1E-O, 4.49E-06 1.23E-06 43.7 NE 1.132-05 4.*62 ENE E

61-16.

6116.

3.71E-05 2.316-O5 1.689-05 1 .082-*05

7. 35E- 06 3. 21E-b0 1.38E-06 9.80E-07

3. 04E-07 2.29E-07 40.6 24.2 ENE E

1.59E-05 7ý.40E-06 5. 356-06 2.20E-06 6 BE-07 1,55E-07 19.7 -ESE SE 6116. 3312 I- 06 9.. 24E.06 4.382-06 1. 34E-06 4.19E-07 1.01E-07 12.3 SEý SSE 6116. 4 .62-07 13.3 SSE 1.10E-05 5 .09E-06 3.45E-06 1. 49E-06 1.02E-07 MAx X/Q 3.85E-05 TOTAL HOURS. AROUND SITE 761.7 SRP 2.3.4 6116. S.0.6E-05 2.17E-05 '1 .42E-05 5.69E-06 1.622-06 3,04E-07

.1 .37E-06 SITE LIMIT 3.58E-05 1.63E-05 1.1OE-05 4.67E-06 3. 04E-07 0TkZ FIVE-PERCENT-FOR THE-ENTIRE-SITE X/Q IS LtMITINC.

Page 35 of 45

Calculation No: NMPAST-01-001.

Constellation Nuclear Services Rev. 2 Date: Dec. 19, 2003 1USNR.C COMPUTER CODE-PAVAN, VESIZ8ON 2.0 RUN DATE: 09-03-02

/PLANT NAME: NINE MILE POINT METEOROLOGICAL INSTRUMENTATION 60.7 METERI WIND SENSORS HEIGHT.:

DATA PERIOD: 1/01/91 ýTO 12/31/01 TYPEOF RELEASE: ELEVATED 130.8 METER ,DELTA-T HEIGHTS: 51.2 METER SOURCE OF-DATA: JOINT FREQUENCY .ISTRIBUTION REPORT (JFD) NINE MILE PCINT NUCLEAR STATIDN.

CQNMENTS; NINE MILE POINT UNIT.2 MAIN STACK TO EAB/LPZi PRO3RAM: PAVAN, 10/76, 8/79 REVISION. IMPLEMENTATION OF REGULATORY GUIDE 1-145 0 RELATIVE CONCENTRATION (X/Q) VALUES (SEV/CUBIC.ZETER)

VERSUS HOURS PER YEAR MAX AVERAGING TIME 0-2 HR X/Q IS DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR (METERS) 0-2 HOURS 0-8 HOURS 6-24 HOURS 1-4 DAYS, 4-30 DAYS ANNUAL AVERAGE IN SECTOR SECTOR 2;*19E* 06 ,6.45E-07 2.67E-07 7.49E-08 1.59EL08 43.7 s S 2256. 9. 70E-07 SSW 1936.. 1.79E-06 6.10E-07 5.46E-07 2.3iE-07 6. 75E-08 1.50E-08 22.3 SSW, SW 1615. 1. .97E306 .71E-07 4:.83E2-07 1.75E-07 '4.06E-08 6.80E-09 32.1 SW N WSW -1615. 8.82E-07 I. 76E-07 5.501E-08 1.03 E-oa IL33E-09 6.0 .WSW

ýw 1555, 88 17E-07

.012E-07 2.75E-07 1,60E-07 4.91E-08ý 9.02Z-09 1.14E-09 6.1 W 0 WNW 1555. 9.81E-607 82E-077 2.38E-o7 8.558-08 1. 96E-08. 3.25E-09 6.3 WNW

ýNW 1555. 1.05E-06 4.56E=07 3:.009-07. 1.21E-07 3.27E-03 6.62E-69 6.7 -3 NNW 1555. 1. 07E-06 4.57E-07 2. 98.-07, 1. 18E- 07 -3. lIE-08 6:.OE-09 7.0 NNW 6~'

N 1555. 1. - 6E-O06 4.50E-07 ,1.16E- 07 3.07E-08. .6;03E-09 6.1 N NNE VNE 1555. 8. S2E-07 3.:45B-07 2-.15E-07 ;.67E-08 1.j52-03 2.86E-09 5.5 NEr.

'9-5sss. 7. 76E-07 . 84E-07 1.71E- 07 s.75E-0O 1. 20E-03 1.76E-09 5.3 NE ENE 1555. 5.13E-07 3.53E-07: 1.56E-07, 4.87E-03 1.17E-08 6.:1 E

1555. 1. 64E-06 7.81E-07 2 .42E-07 7. 64E-03 1.87E-08 16.6 ENE.

ESE 1555. I. 69E-06 7 84E-07 .5.34 E,-07 2.32E-07 7.02E-005 1,.63B-08 21.9 SE

.SE 1.44E-06 6. 866-07 4.-73E-07 2.,11E-07 6.65R-0o 1.62E-08 20.6 1600. SSE SSE 2134. I. 31E-06 6.oE-0.7 4.11E-07 1.77E-07 s. 29E-03 1.21U-08 135.6 MAX X/Q 2.19E-06 TOTAL HD URS'AROUND SITE: 225.9 SRP,2.3.4 1555. 2.43E-06 1.09E-06 7;26E-0'7 3.03E-,07 8.65E-05 1.87E-08 SITE. LIMIT 0.OOE+00 0.'00E+00 0.00E+00, 0. OOE+00 0. OOE+o3 1. 87E-08 00.5 PERCENT X/Q TO AN INDIVIDUAL IS LIMITING.

OX/Q VALUES (SEC/CUBIC METER) FOR FUMIGATION AT THE BOUNDARY:.

DOWNWIND DISTANCE FUMIGATION SECTOR (METERS) X/Q S 2256.. 2.361-05 SSW 1936. 2.51E-05 SW 1615. 2.90E-05 WSW 1615. 2.68E-05 W 1555. 2.77E-05 WNW 1555. 2.77E-05 NW 1555. 2.77E7'05 NNW 1555:- 2.771E-05 N 1555. 2.77E-05 NNE 1555. 2.77E-05 NE 1555. 2.786-05 ENE 1555.. 2.80o05 E .1555. 2.93E-05 ESE 1555. 2.963-05 Page 36 oft45

Calculation No: NMPAST-01-001 Constelation Rev. 2

.Nuclear.Services Date: Dec. 19, 2003 SE 1600. 2.83E-05 SSE 2134 2.25E-05

-3r Page 37 of 45

Constellation Calculation NO: NMPAST-01-O01.

Rev. 2 Nuclear Services :Date: Dec. 19. 2003 1USNRC COMPUTER CODE-PAVAN. V*ESION 2.0 RUN .DATE: 09-03-02

/PLANT NAME: NINE MILE POINT METEOROLOGICAL.INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/01 WIND, SENSORS HEIGHT; A6C.7 METER TYPE OF RELEASE: ELEVATED 130.8 METER DELTA-T HEIGHTS: 51.2 -METER SOURCE OF. DATA: JOINT FREQUENCY DISTRIBUTION REfPORT J(JFD) NINE MILE PO INT.NUCLEAR STATION COMENTS& NINE MILE POINT UNIT 2 MAIN.STACK TO EAB/LPZ PROGRAM: PAVAN, 10/75, 8/79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145 0 RELA1TVE CONCENTRATION (X/Q) VALUES (SEC/CUBIC IETER)

VERSUS hOURS PER YEAR MAX AVERAGING TIME ,0-2 HR XIQ IS DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR (METERS) 0-2 HOURS 0-8 HCURS 8-24 HOURS "1:-4 DAYS 4-30 DAYS: ANNUAL AVERAGE I1N SECTOR SECTOR

6. *3E-08 1.382-00 sW S 6116. 1_73E-06 5.22E-07 2.20E-07 42.5 SSW 6116. 1.49E-06 6.94E8-07 4. 75E-07 2 0BE- 07 6 ..35E-08 1.49E-06 30.1 5.41E- 07 231A2-07 6.82E-08 1.53E-08 43. 3 sw SSW SW 6116. .8.01E-07 WSW 6116. 7. 809E 07 3. 258-07 2.C9E-07 .8.09E-.08- 2.06E- 08 ,3.88E-09 WSW 7..75E-08 2:. 01E- 08 3.84E-09 7".8 W W

WNW' 6116.

6116.

7.30B-07 7.98E-07

3. 07E-07 3.59E-07 2.41E-07 1.018-07 2. 92E-08 6.38E-09 7.6 V N-W 6116. 8 .1SE-07 4.06E-07 2. .6E-.07 ,1.34E-07 4.53E-08 1.20E-08 NW NNW .6116. 8. IOE-07 3.,888E-07 2 . 69E-07 1. 2iE-07 3. 86 E- 08 9.52E-09. 7.2 NEW 2 _E2E-07 1.20E-07 3 -89E- 08. 9.848-09 N N :6116. 7 .74E-07 3.,76E-07 NNE 6116. 7.54E-07 3.52E-07 2.41-,07 3.218-08 7.53E-09 7,7 ENE 6.40E-09 NE ENE 6116.

6116.

6.93E-07 S.337-07 3.198-07 4.,21B-07 2.17E-07

2. 99E- 07 9.36E-08 1.422-07

,2.80E- 08 4.86E-08 1.31E-08 NE E 6116. 1.43E-06 7.05E-07 4 .95E-07 2,30E-07 '7.65E-08 1.99E-08 26.6 I1ý28Eý 06 19,6 ESE ESE 6116. 6.08E-07 4.. 19E-07 1. 87E-07 5. e.5S-08 1.41E-08 ig. 7 6116. 1.068-06 4.988-07 3.4 1E-07. 1.502-07 4.62E-08. 1.098-08 SE 6116. SSE SSE 1. 04E- 06 4.ý76E-07 3 .22E-07 1I.37E-07 4 . C6E-08 9 .i3E-09 15".3 MAX x/Q 1.?58-06 TOTAL HOURS AROUND SITE: 261.7 SRP 2.3.4 6116. 2.19E-06 1.0i-06 6.83E-07 2. 94E-07 8.-,6E-08 1.99E-08 SITE LIMIT 0.0OE+00 0.00E+00 0.00E+00 0.008+00, o. CoE+00 1-99E-08 60.-5 PERCENTX/Q TO AN INDIVIDUAL IS LIMITrNG.

0X/Q VALUES (SEC/CUBIC METER) FOR FUMIGATION AT THE BOUNDARY:

DOWNWIND DISTANCE ,FUMIGATION SECTOR (METERS) X/Q.

S 6116. 1.42E705 SSW 6116. 1.15E-OS SW 611.6. 1.15E-05 WSW .5116. 8.04E-06 W, 6I16. 8.04E-06 WNW 51.16. 8..04-06 NW 6116. 8.048-06 N'`W 5116. 8.04E-06 N 5116. 8.04E-06 NEE 6116. 8.04E-06 NE 6116. 8.23E806 ENE 6116. 8.42E-06 X_

E 61i6. 1.,02E-05 ESE 6116. 1.06E-05 Page 38 of 45

Calculation No: NMPAST-01-001 Constellation Rev.,2 Nuclear Services Date: Dec. 19, 2003 SE 6116. 9:.66E-06 SSE 611:6. i.:OIaE-0 r4 Page 39 of 45

Constellation Calculation No- NMPAST-01-001 Rev. 2, Nuclear Services Date: Dec. 19, 2003 1USNRC COMPUTER CODE-PAVAIe VERSION 2.0 *RUN DATE: 09-03-02

/PLANT NAME: -NINE MILE POINT METEOROLOGICAL INSTRUMENTATION.

,DATA PERIOD:.1/01/97 TO 12/32/01 WIND SENSORS EEIGHT: 60.7 METER TYPE OF RELEASE:.GRoJND.LEVEL RELEASE DELTA-T. EIGHTS: 51.2 METERT SOURCE OF DATA: JOINT FREQUENCY.DISTRIBUTION REPORT '(JF)M NINE MILE POINT NUCLEAR STATION

COMMENT:3: NINE MILE POINT UNI-Te2 COMBINED RADWASTE/REACTOR BUILDING VENT TO EA3/LPZ PROGRAM: PAVAN, 10/7S- 8/79 REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145.

0 RELATIVE CONCENTRATION (X/Q) VALUES (SEC/CUBIC METER)

VERSUSz HOURS PER YEAR MAX AVERAGING TIME 0-2 "R X/Q is DOWNWIND DISTANCE EXCEEDED DOWNWIND SECTOR (METERS) 0-2 HOURS 0-8, HOURS 8-24 HOURS 1-4 DAYS. 4.*30 DAYS ANNUAL AVERAGE IN SECTOR SECTOR S

S 1945. 4 .65E-O5 2.51E-05 9.465-06 .3.62E- 06 1. 12E-06 1.0.. 3 1695. .5.47E-05 3i10-05 2.34E-05, 1.278E-OS 5 .25E-06 1.79E-06 13.1 SSW

2. 185-05 24.4 SW 1381.

1381.

8,. 52 05 9.14E-05 S."12E-05 5.13E-05 3.SiE-05 3.ES-05 2.06E-05 9.46E-U06

8638E-06

3. 40E-06 2.79E-06 27.1 WSW z w 1381.. 1 .IOE. 04 6.l16E-'05 4.. 61E-05 2.46E-05 1 00E-.05 3,33E-06 31.7 W NW 1. ,IE* 04 6.25E-05 4. 71E-05 2. SSE-05, 0..6E-05 3.59E-06 28 .1 WNW.

1381.

6.28E-05 4.'91E-05 ,2A89E-05 1. 35E-05 5.31E-06 21.,E N*w NNW 1381. 1. 168E 04 NNW 1381. 1024E704 1.065:-05 3,21E-05 1.48E 5.738-06 21.4

5. 468-0"6 N 1381. I. 17E- 04. 738E.-.05 5.70E-05 3.26Eý05 .1.46E-O05 34..9 N NNE 6. 868-05 5 *25E-OS 2.94E-05 1--.-7E,65 4. 59E-06 NE 1381. 1. 42E- 04 8.18- 05 6.22E- 05 3.42E-05 1.45E-05 5. IOE-06 43.1 NNE -6" 1381. 1,24E-04 ENE tNE 136861. 8. o*E- 05 8.139-05 3.69E-05 1.70E-OS 39.2 E 4.70E-05 3, O0E-0S0 2.03E-05 8.85E-06 3.22E-06 20'.6 Ei 6.22E-05 4..34E-04 1:7,9 ESE ESE 1686. 3-.57E-05 2.70E-05 .6.23E-06 2.16E-06, SE 1743., 3. 85E-05 2.32E-05 1. t-5-O 9.54E-06 3.98E-06 1.36E-o6 11.8 Se.

SSE 2094., 2.058-05 1.50E-05 7.56E-0"6 2.E4E-06 8. 54E-07 ,9.9 SSE MAX,- X/Q 1. 4;2E- 04 TOTAL HOURS AROUND SITE: 383..5 SRP 2.3.4 1381. 2.4SE-04 1.34E,-04 9.97E-05. 5.21H-05 2.05E-05 6.56E-06 SITE LIMIT 0.00E+00 0.OOE+O0 0.-00+00 0., 00E+00 0. OOE+00 6.56E-06 oý6.s PERCENT X/Q TO AN ItnIVIDUAL IS LIMITING.

4:

Cr' Page 40 of 45

Constellation Calculation No: NMPAST-01-001 Rev, 2 Nuclear Services: Date: Dec. 19, 2003 IUSNRC COMPUTER CODE-PAVAN. VERSION 2".0 RUND.,DATE.: 09:-03-02 IPLANT NXME: ýNINE MILE POINT' METEOROLOGICAL INSTRUMENTATION DATA PERIOD: 1/01/97 TO 12/31/01 WIND SENSORS HEIGHT: 60.7 METER TYPE OF RELEASE: GROUND LEVEL RELEASE DELTA-T HEIGHTSý 51,2 METER SOURCE OF DATA: JOINT FREQUENCY DISTRIBUTION REPORT (JFD) NINE MILE POINT NUCLEAR STATION

-COMMENTS: NINE MILE POINTUNIT 2 COMBINED.RADWASTE/REACTOR BUILDING VENT TO EA3/LPZ PROGRAM: PAVAN, 10/75, 8/79'REVISION, IMPLEMENTATION OF REGULATORY GUIDE 1.145 0 RELATIVE CONCENTRATION (X/Q) VALUE$ (SEC/CUBIC METER)

VERSUS HOURS PER YEAR MAX AVERAGING. TIME 0-2 HR XK'Q .is DOWINWIND DISTANCE EXCEEDED DOWNWIND:

SECTOR (METERS) 0-2 HOURS 0-8 HCURS 8-24 HOURS 1-4 DAYS 4-30 DAYS ANNI JAI AVERAGE IN :SECTOR SECTOR

3. 586-o6 1, 69E-06 44.92E-07 1;09E-:07 143 s S 6116. 1i.306-05 5.90E-06 SSW 6116. 1..8E-05 6.11E-06 4. 15E-06' 1. 79E606 5.37E-07 1.23E-07 .392.7 SSW 1 .616ý2-05 19.7 SW SW 6116. a.15E-06 5.47E606 2. 30E406 6.66E-07 1.46E-07 WS~W 6116. 2. 07E-05 8, 92E-06 5. 66E-06 2.,36E-06 6.37E-07 1.29E-07 24.1 wsw W 6116. 2.74E-05 1.17E-05 7 ,61E-06 3,029-06 7.99E-07 1.57E-07 30:.1 W, WNW 2.76E-05 1. 18E-05 7.7;2E-66* 8.19E-07 1.63E-07 26.8 WNW 6116. 3 .37E-06o NW 6116. 2. 54E-05 I."17E605 7.8 9E-06 3.398-06 1. IE-06 :2.29E-07 20.15 NW, NNW 6116. 2.92E-05 1.346-05 9. 03E-06 -. 14E-06 2.57E-07 23,1 NNW N 2.78E-05 '-.27E805 3.676-.06 2.43E-07" 27.7 N 6116.

NNE 6116. 3 .03E-05 -. '33E-05 9.:98E-07 2.08E-07 27.9 NNE 3 .85E-05 1.(095- 05 1.1O9E-06 2.40E-07 43.7 Ns 6116.. *.66E-05

'ENE 3 .716-0S L. 67E.05 1,. 12E-05 1.3s5-o6 2.936-07 40.6 ENE e--

E 6116. 3.,16E-06 E 2.31E-0S ,-07E-05 7. 28E-06 2,16E-06 ý9.56E-07 2.21E-07 24.2 ESE 6116.- 1. 58E-05 7.32E706 4..98E-06 1.32E-06 .6- SOE -07 1,50E-07 19.7 .ESE SE 9.246-06 4.. 36B-06 2.:99E-06 4.112-07 9.8OE-08 12.E SE 6116.- 4635E-07 9. 83E 13..6 SSEE SSE 1.IOE-05 5'.06B-0"6 3.42E-06 1.*47E-06 MAX X/Q 3.85E605 :OUND SITE:

TOTAL HOURS. AR~ 761.6 SRP 2.3.4 6116. 4.99E=05 2.13E805 1:.40E-05 5. 55E-06 1.48E-06 2.93E-07 SITE LIMIT 3.58E-05 1.62E-05 1.09E-05 4.59E-06 1.-3E-06 2.93E-07 OTHE FIVE-PERCENT-FOR-THE-ENTIRE-SITE R/O :S* IAMITIMG.

6' Page 41 of 45

cA~7~- ~ Calculation No: NMPAST-01-001 Constellation Rev. 2 Nuclear Services Date: Dec, 19, 2003 Appendix C - Listing of Files on DATA CD-ROM for Calculation NMPAST-01-O1 Page 42 of 45

L(8 Hz2ic4 ~c-$'04 Calculation No: NMPAST-01 -001 Constellation Nucfear Services Rev: 2 Date: Dec. 19, 2003 Note: This directory listing does not include the calculation document, cover page and review checklist files.

Directory.. o D:\

08/05/2002: 11:04,-AM. 20,992ZTerrain Height'Estimates..xls 0.8/23/2002 11:15 AM 58;368 Revised NMP_606_JFD_1997-2001 for CNS.doc Directory of D:\0.5% Sector Dependent Calculations 12/19/2003 05:00 PM <DIR>

12/19/2003 05:00 PM <DIR>

08/29/2002 08:34. AM 331,264 UI. Main Stack to EAD E..xln 08/28/2002 07:54 PM 332;288 U1 Main Stack to EAB - EsE.xls 09/06/2002 10:03,AM 331,264 UI Main Stack to EAB - SE.xls 08128/2002 07:56 PM 331,264 U1 Main Stack to EAB -SSW.xls 12/19/2003 01:55 PM 332,288 U1 Main Stack to LPZ - E.xls 08/28/2002 08:10 "PM 331,776 U1 Main Stack.to LPZ - ESE~xls 08/28/2002 08-14 PM 331,264 UlVMain Stack to LPZ - SW'xls 08/28/2002 08i1S PM 329,1i2b U1 Main Stack. to LPZ - WSWxls 12/19/2003, 03:48 PM 333,312 U1 Reactor BLDG Blowout Panel to EAB- E..xls 08/28/2o0o2 00:10: PM 331,264, U.Reactor.BLDC Blowout Panel to SW.xls 12/19/2003 03:43 PM 330,752 U1 Reactor BLDG Blowout Panel to BAB- WSW.xls 08/28/2002 08:21 PM 332,288. Ul..Reactor BLDG Blowout Panel to LPZ - SE.xls

.09/06/2002 10:40 AM 332,288 U1 Reactor BLDG Blowout Panel to SSE.xls 08'/28/2002 08:23. :PM 3322889 11 Reactor BLDG Blowout Panel to LPZ - SSW.xls 08/2/2002' 08:25 PM 331,264 U1 Reactor BLDG Blowout. Panel to LPZ - SW.xis 08/28/2002 08:34 PM 332,288 U2 Combined Radwaste and Reactor BLDG Vent to.EAB - SSE.xls 08/28/2002 08:35 PM 331,264, U2 combined Radwaste and Reactor BLDG Vent to.BAD - SW. Xls 12/19/2003 01:55 PM 332,28& U2 Combined Radwaste and Reactor Vent to EAB' - WSW.xls 08/218/2002: 08137 PM 332,288 U2 Combined Radwaste and Re-ctor Upn~t to LPZ -SE.xls 08/28/,200'2 08:39 PM 332,800 U2 Combýined RadwaSte and Reactor BLDG, Vent to, LPZ -SSE.xls 08/2S/2002 08:40 PM 332,288 U2 Combined Radwaste and Reactor BLDG Vent to LPZ - SS.xls 08/28/2002 081:42 PM 331,264. U2 Combined Radwaste and Reactor Vent to LPZ -SW~xls 09/06/2002 10:53 AN 332,288 U2 Main Stack to LPZ -ESE.xls 08/28/2002 08:28 PM 331,776 U2 Main Stack to LPZ - S..xls 08/28/2002 08;29 PM 331,776 U2.Main Stack to LPZ -. SE~xls

ý08?28/2o002 08:30 NM 331, 264' U2 main Stac'k to LpB - OslE.xlIZ 081/28/2902 08:31 PM 331,264 U2 Main :Stack to LPZ -SW.xls 08/269/2002 0,8t33 PM .329,72R U2 Main :Stack. to LPZ -WSW.:xls 28 File(Is) 9,287.168 bytes Directory of D:.-\5% *Site Limit Calculations 22/19/2003, 04:32 PM <DIR>

12/19/2003 04:32 PM <DIR>

12/19/2003 04;21 VM 3,603,456 5W EnvelopeO.xls 12/19/2063 04:i32 PM 16:,384 Intermediate Time Calculations.xls 12/19/2003 04:19 PM 359,936 Unit 1 Main Stack to EAB.xl!

12/19/2003 04;:19. PM 367,616, Unit 1 Main Stack:to LPZ.xls 12/19/2003 04:20 PM 354,304 Unit I Reactor BLDG Blowout Panel to EAB.xls 12/19/2003 04:2"0 PM 355,840 uhit.2 Combined Radwaste and Reactor BLDG Vent to EAU.XI:S 12/19/2003 04:20 PM 372,736 Unit 2 Main Stack to EAB.xls 12/19/2603 04:20 PM 369,664 Unit 2 Main Stack to LPZ.xls 8 File(s) 5,799;936 bytes Directory of D:\Input Files 11/18/2003 02-:24 PM <DIR>

11/18/2003 02:24 PM <DIR>

09/26/2002 10:04 AM -7,913 unit 1 Main Stack to EAB and LPZ-inp 08/26/20;2 10:04 AM 7,441 unit Reactor Bldg Blowout Panel to EAB and LPZ.:inp 08/26/2002 AM 7,.441 unit 1 Turbine BldS Blowout Panel to EAB and LPZ.inp 09/03/2002 09:444. AM 7,91ý3 Unit 2 Main Stack to EAB and LPZ.inp 08/26/2042 30:04 AM 7.442 Unit 2 Main Steam Tunnel to EAB and LPZ.inp 08/2.6/2002 10:04 AM 7,444 Unit 2 Post Accident Samp to .EAD and LPZ,.inp Page.43 of 45

0 G.O~~~4 Calculation No: NMPAST-01-001 (49 Constellation Rev. 2 Nuclear Services Date: Dec. 19, 2003 08/26/2002 10:04 AM 7.450 !nit 2 Reactor'Bldg to EAB and LPZý.inp 08/26/2002 10:04 AM 7,448 Unit 2 Stby Gas ,Bldg to0EAB and .LPZ.inp 8 File(s) .60,492 bytes Directory of D::,\Maximum Stack XQ. Distance

//18/'2o03 02:24 PM <DIRý.

11/18/2003 02:24 PM :DIR.

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08/27/2002 03ý10 PM 7,91.3 100 and 250 _np 08/27/2002 03:10 PM 7i913 i000 and 1250.inp 08 /2V/2602 03:20 PM 602,588 1000AN-1.out 08/27/2002 03:20 PM, 5 98,239: 100AND-1.out 08/27/2002 03:.10 PM 7,913, 1500 and 1750.inp 08/27/2002 03:20 PM 604,359 150OAN71.out 08/27/2002 03:10: PM 7,913 2000 and 2500.inp

.08/27/2002 03:20 PM 605,411 2000AN-~.out 08/27/2002 03:10 PM 7,913 3000 and 3500.inp 08/27/2002" 03:20 PM 609,698 3000AN-l.out 08/27/2002 03:10 .PM 7,9k3 4500 and 5000.inp 03:- 20 PM 615,621 4500AN-1.out

ý08/2*7/2002 03:10 PM 7,913 500 and 750.inp 08/217/2002 03:20 PM 597,141 500AND-1.out 08/27/2002 03:10 PM 7,913 510 and 535.inp 08/27/20.02 03:20 PM 596,977 50AND-I..Out 08/27/2002 03.10 PM 7,913 52S and S50.inp, 03:20 PM 596,679 525AND-1.0ut 081217/2002:

08 /27/2002 03:10 PM 7,913 5500 and 6000.inp 08/27/2002. 03:20. PM 615,867 55010AN-1.Uct 08/27/2002 03:10. PM 7,913 600 and 650.inp 08/27/2002 03:20 PM 595,555 600AND-.1.out 08/27/2002 03:10 PM '7,913 6500 and 7000.inp.

08/2-7/2 002 03:20 PM 617, 663,ý 6500AN-1.uuL 7 913 700 and 850.inp 03:20 PM 08/27/2002 597,4 91 700"AND-l.out 08/27/2002 03:10 PM 7,913 8000 and 9000.inp 08/27/2002 03:20, PM 602,625 800.OAN-.l.out 08/27/2002 02:07 PM 224 run uniti.bat 08/27/2002 129,536 Unitl Max Stack XQ (Scoping):.xls 04:51PM 30 File;(s) 8,696,456 bytesý DireCLOty of0,D\a:?ýinum Stack XQ:Distance\Ulnit 2 11/18/2003 02:24 PM <DIR>

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08/27/2002 02:46 PM 7,913 100 and 250.inp 08/27/2002 02:48 PM 7,913 1000 and..1250.inp 08/27/2002 03:21 PM 602,399 10o00Ao1-.out 08/27/2002 03:21 FM 597,841 100AND-IOUt 08/27/2002 ,02:49 PM 7,91i3 1500 and 1750.inp 08/27/2002 '03:21 PM o0,o037 0sooAN-1.ot 08/27/2002 02:53. PM 7,913 2000 and 2500.inp 09/27/2002 03':21 PM 606,903 2000AN-i.out 08/27/2002 02:55' PM' 7,913 3000 and 3500.inp 08/27/2002 03:21 PM 610,393 3000AN-I.out 08/27/2002 021:56 PM 7,913 4500 and 5000.inp 08/27/2002 03:21 PM 613,827 4500AN-1.Iout 08/27/2002 02,57 PM 7,913 500 and 750.inp 08/27/2002 03:20 PM 597,739 500AND71.out 08/27/2002 02:58 PM 7,913 610 and 535.inp 08/27/2002 03:20! PM 597,841 510AND-I.out Page 44 of 45

t.47 1C, 0 Constellatio In Calculation No: NMPAST-O1,OOI Rev. 2 Nuclear Service Date: Dec. 19, 2003 08/27/2002 02':59 PM 7,913 525 and 550.inp 06/27/2002 03:21 PM 598,435 525AND-1..OUt 06/27/2002 03:00 PM 7,913 5500 and 6000.inp 08/2 7/2002 03':21 PM 616, 055 55ooAN-1.out 06/27/2002 03:02 PM 7*913 600 and 650.inp 08/27/2002 03.21 PM 590,117 600AND-I.out 08/,27/2002 0.3:02 ýPM 7,913 6500 and 7000.inp 08/27/2002 01-21 PM 917,883. 6500AN-1.out 08/27/2002 03:03 PM 7,91,3 700 and 850.inp 08/27/2002 03;,21 PM 597,689 700AND-,.out 08/27/2002 03:04 ýM 7,913 8000 and 9000.inp 08/27/2002 03:21 PM 607,754 800CAN-21.out 08/27/2002 02:07 PM 224 run-unit2.bat 08/27/200.2 05:51 PM 130,048 Unit 2 Max Stack XQ (Scoping1..xls 30 rile (s) 8,708,967 bytes Directory of D:\Output Files 11/18/2003 02:24 PM <DIR>

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109/03/2002 09:58 AM 609,639 UNITIM-I.out 09:58 AM 571,812 UNIT1R-l.OuL 09/03 /2002 09:58 AM 571,812 UNITIT-2.Out 09/03/2002 09588 AM 612,897 UNIT2M-1..out 09/03/2002 09:-58 AM 571,256 UNIT2M-2.out 09/03/2002 09:58 AM 571.256 UNIT2P-I.Out 09/03/2002 09:58.AM 571,256 UNIT2R-lýOit 09/03/.2002 0-9f58 AM 571,256 UNIT2Sý1.out 8 File (8) 4,651,184 bytes Page 45 of 45

Calculation Cover Sheet Calculation No. NMPAST-02-O01 Rev. 2 No. 6fPagR e3 theAll, NMJ' Unit I Title Suponor ofAAtimQoheric Calculation kTealnical Center and Units Disersion i iand 2 Control PRno*. (XJOsj Coefficients !ntakesat,for Releases Rev I)Name Signature Date______

Prepared:By Shane*Gardner Checked By James Heffner _...____

ApproveBy.., Tara Neider ..... _' "_'__ '"___

Rev. I Nainc Signature Date Prepared By Shane Giardner _____

CheckedBy Jamies Heffnar Aproved By' Tarn Ncidcr____________

Desription of Changes This calculation revision is in response to the availability of revised meteorological data, from NMP. This revision incorporates thexresults of the revised meteorologicaldata into the body of the calculationi.e.' the X/Q results in Tables 3.3.3 and 3.3.4 have been recalculated with the new meteorological data. Also, this revision adds.the calculation:of X&Q values at the Unit I Technical Support Center. This revision funiher includes changes to resolve minor editorial issues; Affected Pages: Cakulation 'Cover Sheet:(Title); all page afther Rev..2 Name . ure Date Prfared By Shane Gardner j,:2]* v'-" 2Iai3 " '

Cheked By David Matchick l9ne d'-ik*' ic/* I Approvedy Ly SmiBth -,'

Deseription.of Changes /

Tho purposeO. this revision*,is to respond to comments made in a third party review performed byyNISYS Corp. at he request ofNMPNS. Several comments weremade and te reader is referred to the NISYS doeunutNISYS-] 169-DVOOI/RO for more detail. CNS and NMPNS agre.:ctoa p:Wn to resolve a selection ofthe NiSYS comments (see CNS-03-21 8.91V4/03 and electrnic correspondence from Timothy U. Kurtz to Shlano Gardnser November 6,2003, "Rf: CNS Comments on NISYSRoview of XIQ Calculations"). C NS-03-218 provides a description regarding how~the comments were addressedand provides the baa is for indorporatinee comments into this calculaxioun. More specifically, tho followintg comments were addresd.

NISYS Comment No. Description Affected Page(s) a, include a scale drawing (compass "rose") Appendix A lb statementaocmmuing conformance to Safety Guide 23 4, 26 (Refs. 29 &30),

2a first part olyý,jusif6tiou of assumltions 8-10 CNS QA Form: OA-3.2.1. Rev. 0

qzI:C0(.-0 incorrect conversions from Euglisb.to r*ctric units 6, 8,, 16-19, 22-24 4a Sa add adetailed listing of filae on CD be provided Appendix Di building wake area input Only comment.4aiWpacted the,results ofthe calculation. 'This coment changed X/Q estin taL'me parameters for seveal orth ARCON9 6 computr nm3,and t*hrfore impacted the ItIwas

,revised resuLts were compared against the prmeioas reults from revision I ofthiscalculation,respect t the revised letennind that the p~revious revision I:re*sults were nservatve and boun~ding with intake. The esU M t ofthe changes in the X/Q values occured for XIQs 6t the Unit I Conttal Room Mos.

following is a cataloguo of the changes in the X/Q vOlues:

Release Point Receptor Point Avenge Change in X/Q (*/a)

Unit I Control Room -4.1 Unit I Reactor Bldg. -2.6 Unit I TurbIno BhlgX Unit I Control Room Unit 1 Control Room -HA.4 Unit I Main Stack Unit I Control Room -4.4

Unit I Combitwd RadWastc/Rx Vent Unit I Control Room -1.8 Unit Z PASS Panel -0.6 Unit 2 SGTS Sidg. Unit 1 Control Room Unit I Control Room -0.9 Unit,2 Main Stram Tunnel Unit I Control Room -3.8 Unit 2:Main Sivk U nit 11Tech. Support Center -03 Unit 2 Main Stack Unit 2 PASS Panel Unit 2 Control Room Unit,2 SOTS Bldg. Unit 2 Control Room -0.1 Uoit 2 Main Stack Unit 2 Control Room ,-03 To.addition to the cluungf indicatedabove, the,calculatioa was.frdwrrevisedl to incorporate; minor editorial chaiges.

Affected Pages:Calculation Cover Sheet (itle); all pages thereafter GNS QA Form: OQA3.2, Rev. 0

14.2.C4'~i 53 Calculation Review Checklist Calculation # NP1PAST-oZ-Wo Rev . Z.

Circle, as approPriate. the YesINo/NA for all items Correct calculation format .. ................. .............................................. 9No/NA Correctness of assumptions .......................................... ( o/NA Adequacy of assumptionbasis ........... ....... .......................-......0 ...... *..... No/NA parameters s(

Correctnes sseof para.etr.. ........................................ .................... No/NA Appropriate choice of method ....... ......................... ...................... o/NA Adequate: documentation of method ............................................................. o/NA Correct applioatiorrofl method ..................................................... . ..... (o/NA Correctness of results/conclusions .. .... ....... ......... o*NA Adequate Referenced'it ............. . ..... . ....... ........... YeNo/NA If computer software was used to perform the calculation, the following elements shall, also be considered:

Proper software verification and verification documentation .... .(e o/NA o..........t..

Correctness of input: parameters..............7................................ 3N/A.

Correct information in analysis calculation ................................................. NoiNA

'Correct interpretation of results .......... ...... ...... ......... .... )....A Date __ _ __ _ _

Signature

NSQA Form: QA-3.2.2, Rev. 0 a

C onstella ion Calculation No: NMPAST-02-001 Rev. 2 Nuclear Services Date: December 22, 2003 Table of Contents

1. Objective .................................................... ...... I .......... . !..

................. .4

2. Background ........... ............................ ............................. 4 2.1. Applicable Regulations and Commitments: ............................ .. .... 4

3. M ethodology.............................................................................................................. ......... 4

4. Computer HardwarelSoftware Usage ... ... .........................

........ 5 4.1. Description of Hardware Used ........ ............................................ 5 4.2'. Description of Softw are Used ........ ....... ,.........., . i ..................................................... 5 4.2.1. S oftw arre V erification ................................ . .................................................................. 5

5. Inputs ...... ........ ,1:,........ .................. ........................................................................ 5

ý5.1. Meteorological Input ...... ......... ............... . .......................................... 5, 5.2. Release/Intake Distances and Directions..................................................... .............. ý5 5.3, Release/Intake Elevations ....................I.. .. ..................... 6 5.4. Building Dimensions Related Pertinent to Wake Area Calculations .... ......... .6

6. Assum ptions ..... ....................... ................... ............................ ........... o...................8

7. Calculations and Results .............................................................................................. 10 7.1. Release/Intake Distances and Directions Calculations ..................... 0.......

0 7.2. Building W ake A reas; ........ ....................... ...................................................................... 160 7.3. X/Q Values......... . .............. ....... .......... ............ 20

8. C onclusions ................................ !.......... 7. .................................. ........ ...... ....... 25..........

25

9. References. ...... . ........... ................... w.......... 25 A ppendices .......... I........... ........... ......... .......... ....... . ............................................ 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

Calculation No: NMPAST-02-0O01 Rev. 2 Nuclear Services Date: December,22, 2003 List of Tables Table 5.2.1. Release/Intake Distances-and Directions ....... . ....... 6 Table5.3.1. Releaselintake Elevations;....... .... ...... .............. ......... 81 Table 7.1.1. Summary Tableiof Calculated Coordinates of Release/Intake 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 Table 7.1.3. Summary Table of Distances and Directions of Unit 2 Releases to the Unit I Technical Support Center ............................................................................................. 15 Table 7.2.1. Calculated Building WakewAreas ............. ...... ................. ................ 19 Table 73.1 ARCON96 Distances and Directions Input ....................................................... 21 Table 7.3.2. List of CommonlDefaultInput Data to ARCON96 ................... ,...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 I 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 2 of 37

Calculation No; NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22,2003 List of Figures Figure 7.1.1. Schematic of Coordinate Used In Calculating ReleaselIntake Distances and Directions ,,. ........,I...................... ...... a......................................................................... 12 Page 3 of 37

.Calculation No: NMPAST-02-001 Rev. 2 Nuclear Services Date: December 22,2003

1. Objective The purposeof this calcUlationmis to determine conservative estimatesof atmospheric dispersion coefficientS (NQ)for the Nine Mile Point Unit I and 2 Nuclear Station control room air intakes for release points defined heroein.

.2. Background Nine Mile Point Nuclear Station (NMP) has requested the services of Constellation 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 Alternative 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 X/Q 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 habitability assessments (Ref. 5) has beoen implemented as necessary. The

.regulatory guidance for analyses associated with the use of 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 conformssto 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 XIQ values based on'hourly meteorological data. The X/Q values calculated are hourly, normalized concentrations,. These values are then averaged to provide X/Q .values for time periods ranging from 0 to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months . Ammore 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 X/Q values for all releases to each of 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 to the 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

Co set ellaio Nula Calculation No: NMPAST-02-001 Rev. 2 Constellation Nuclear Se*rviCes Date: December 22,2003

4. Computer Hardware/Software Usage 4.1. Description of Hardware Used All computer 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 guide (Ref. 2).

Microsoft Excel was utilized to calculate distances and directions for releasefintake scenarios not readily available by reference.

412.1. Software Verification ARCON96 has been verified and validated (Ref. 6) in accordancewith 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 were verified in the same manner as technical reports (Ref. 7).

5. Inputs 5.1. Meteorological Input

1. Upper level wind measurement height = 199'* 60.66 meters (Ref. 8).

2. Lower level wind measurement height = 31' = 9.45 meters (Ref. 8).

3. Meteorological input data provided in ARCON96 MET file "NMP 1997-2001 ARCON96 Rev ,1.txt" (Ref. 27). This data is a :revision to previously Used data (Ref. 9). This file has been renamed "NMPRI .MET" and is included on the attached disk.

5.2. Release/Intake Distances and Directions Distances and sector bearings for the: various releases for both Units 1 and 2 are provided in several previous calculations performed by Meteorological Evaluation Services (MES), Inc.

Table 5..1 summarizes this input data.

Page.5 of 37

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear: Services Date: December 22, 12003 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 and intake points,. Unless otherwise indicated, the elevations listed are above plant grade.

54. Building Dimensions Related Pertinent to Wake Area Calculations Unit I Turbine Building

1. Building height above grade = 369' 3 1/2"-261' = 108'3 1/2" = 33 meters (Ref. 10).

Unit 2 Turbine Buildinq East-west dimension = 338' = 103.02 meters (Ref. 11).

2. North-south dimension = 140' = 42.67 meters (Ref. 11).

3., Building heightabove grade= 120'= 36.58 meters (Ref. 12),

.Unit 2 Reactor Building

1. Outer radius = 85' 6" = 26.06 meters. (Ref. 13.)

2. 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 Distance Sector Reference (ft) (m) Bearings"]

Releases to Unit I Control Room Intake 1 a ! Unit 1. 340 103.6 1490 SSE Table 1 Unit 1 Reactor Building Blowout: Panel

-Control Room Intake Ref. 18 Unit 1 Turbine Building Blowout Panel121 / Unit 1 236 71.9 1170 ESE Table 1

,Control Room Intake Ref. 18 Unit 1 Main Stacl< / Unit I Control Room Intake 400 121.9 1660 SSE Table 1 Ref. 18 Unit:2 Combined Radwaste & Reactor Building 615 187 2460 WSW Page 2 Vent/ Unit 1 Control Room Ref. 17 Unit.2 Main Steam Tunnel I Unit 1 Control Room 595 181 2460 WSW Page.2 Ref. 17 Unit.2 Standby Gas Treatment System Building.i 800 244 2420 WSW Page 2 Unit 1 Control Room Ref. 17 Unit 2 Post-Accident Sampling System.Pane! 1 660 201 :230u SW Page 2 Unit I Control Room ..... I Ref. 17 Page 6 of 37

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003 Release/Intake Distance Distance Sector Reference

. ( m) B ea r in g [ !l ,

. . . . . .__f Unit 2 Maih Stack / Unit 1....Control Room 1355 t.)

1413 2330 SW Page 2 R ef. :17 Releases to Unit I Technical Support Center Unit I Reactor Building Blowout Panel'F] / Unit 1 343 104.5 86" ESE Table I Technical Support Center 1 __[21__6__ Ref.. 18 Unit 1 Turbine Building Blowout Panel'2 1 / Unit 1 328 100.0. Table 1 Technical Support Center Ref. 18 Unit 1 Main Stack / Unit 1 Technical'Support 330 100.6 140o SE Table 1 Center, Ref. 18 Releases to Unit 2 Control Room Intakes Unit 1 Main StackI Unit 2 Control Room West- 740 225.6 i1 1.i,( 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 1'150 ESE Table 1 High Ref. 18 Unit 1 Main Stack / Unit.2 Control Room East- 800 243.8 115') ESE Table 1 Low _ Ref. 1,8 Unit 2,Main Stack / Unit 2 Control Room West- 937 286 2250 SW Table 4 High Ref. 16 Unit 2 Main:Stackx IUnit 2 Control Room West- 919 280 2250 SW Table 4 Low .Ref. 16 Unit 2 Main Stack / Unit 2Control Room Eastý 843 257 202.5* SSW Table 4 High _ Ref. 16 Unit 2 MainStack I Unit 2 Coritrol:Room East-, '846 258 202.50 SSW Table 4 Low .... .__ Ref. 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

Calculation No: NMPAST-02-001 0 Constellation Rev. 2 Nuclear Services Date: December 22, 2003

.Table 5.3.1. Releasellntake Elevations Point of Interest Elevation Elevation Reference

_ft) (m)

Unit I Main Stack 3.50 .106.7 Page 11-35, Ref. 15 Unit I Reactor Building Blowout Panel"! 78.9 24.0 Ref. 10 Unit 1 Turbine Building Blowout PanelTLJ 72.4 22.1 Ref. 10 Unit-2 Main Stack 429 1308 Table. 1, Ref, 16 Unit.2 :Combined Radwaste & Reactor 187 57 -Section 11.3.3.1, Building Vent. Ref. 19 Unit 2 Main Steam TunneiL2] 45.08 13.7 Ref. 20 Unit 2 Standby Gas Treatment System 23.5 7.2 Ref. 21 Building [2]

Unit 2 Control Room Intake West-High t 3: 36 11 Ref. 22 Unit 2 Control Room Intake West-Low'*] 15.5 4.7 'Ref. '22 Unit,2 Control Room Intake East-High' JJ 52.75 16.1 Ref. 22 Unit 2 Control Room Intake East-Low%'J 19 5.8 Ref. 22

Notes,

1. Elevation: relative to bottom of, blowout panel,

2. Elevation relative to bottom of louvered exhaust.

3. Elevation relative to bottom ofrintake.'

6. Assumptions

1. North-south dimension of Unit 1 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'-= 9967 meters (Ref. 23). This assumption is taken to approximate the dimension ofthe Unit 1 Turbine Building for the purposes of calculating the buildihg wake area.

3. Unit 1 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-approximate 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 concrete curb surrounding the vent.

location. This assumption is taken .to approximate the vent release height as it is not apparent from the references.

Page 8 of 37

> Constellation Cn e i

'Calculation No: NMPAST-02-001 Rev. 2 Nuclear Services Date: December 22, 2003

5. Unit 1 releases to Unit I Control room intake building wake area is conservatively

.assumed to be equal to one half of the east-west Unit I"Turbine Generator Building cross-sectional area. This assumption is to account forthe complexity of the dense

,building cluster atthe NMP site forwhich 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: building wake area is conservatively assumed to be equal to north-south cross sectional area of 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 slightly greater 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 equal to north-south cross-sectional area of the Unit 2 Turbine Building;.

As theý 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 slightly greater than the value determined from this assumption. Therefore, this assumption conservatively results 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, neighboringi 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 m 2 (Ref. 5) for a.zero wake term. This assumption is. made because.the Combined Radwaste &

Reactor Building Ventand 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 areaeis conservatively assumed to be equal to 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 wake area. This assumption conservatively results in.higherX/Q values.

11. Unit2 Main Stack release is assumed to be a ground-level release as opposed to a stack releasepin ARCONg6. This assumption is made. because the NMP stacks are generally located in close proximity to the site building. cluster. The height of the stacks Page 9; of 37

1AtConstel Calculation ao. NMPAST-02-001 Constellation Rev. 12 Nuclear Serices lDate: 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 proper qualification of stack configurations mustbe made in order tor assume a stack release. Therefore, to alleviate the regulatoryrisk and to assure conservative X/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 c ross-sectional area. 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 slightly greater than

-the value determined from .this assumption. Therefore, this assumption conservatively results in higher X/Q values..

13. Unit 1 Main Stack and Reactor Buiiding Blowout Panel releases to Unit 1 Technical Support Center building wake area is assumed.to be 0.01 m 2 (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 it is difficult to characterize the building wake area. A zero wake term assumption conservatively results in higher X/Q values..

14. 'Elevation change from 'the mid-pointof the Unit; I Turbine Building Blowout Panel to Unit I Technical Support, Center is 62' or 18.9 meter (Ref. 18). The elevation of the mid-point of the Unit 1 Turbine Building Blowout, Panel is approximately (354' + 334') /2

- 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. Release/intake Distances and Directions Calculations Table 5.2.1 lists 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 1 Turbine Building blowout panel, (3) Unit 2 Main Steam Tunnel,, (4)

Unit 2 Combined Radwaste & Reactor Building Vent, (5) Unit 2 PASS Panel vent and (6) Unit 2 StandbyGas Treatment Building vent. Furthermore, the MES calculations also fail to disclose thedistances and bearings for the Unit 2 releases tothe Unit 1 Technical Support Center. The data listed in Table 5.2.1 was used to calculate the distances-and directions for the above release/intake 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

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003 The, calculations were 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 intake were 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 1 Main. Stack, (3) the Unit I 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 calculate the.distances and directions tojthe Unit 1 Technical Support Center for the following Unit2 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(9),

Ay = d..cos(O) and

= 1i800() '

a=.t a -, I __X 0 atarf'l 9x+/-8 LAy) 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," cx is the angle relative to the negative y-axis (180 degree or south) and d is the distance between'two points. Table 7.11.1 shows the coordinates calculated 'for 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 7.13shows the calculated distances and directions-for various releases to the Unit 1 Technical:Support Center.

Page 11 of 37

4'-1C. ',6 --cý Calculation No: NMPAST-02-001 A Constellation Rev. 2 Nuclear Services Date: December 22, 2003 True. North Plant North y Unit 2 Main, Stack x

Figure 7.1.1. Schematic of Coordinate Used In Calculating Release/Intake Distances and Directions Page 12 of 37

Calculation No: NMPAST-02-001 Constellation ReV. 2 Nuclear Services Date: December 22, 2003 Table 7.1.1. Summary Table of Calculated Coordinates of Releasellntake Locations for-Units l and 2 Coordinates, FROM TO Ax:(ft) Ay(ft d (ft)I d (n) j0(deg) x (ft) I y(ft) Location Unit 2 Main Stack IUnit 1 Control Room Intake -..1082.151 -815.46113551 413 2331 1082 -15.46 Unit 1 Control Room Intake Unit 1 Rx Bldg. Blowout Panel Unit 1zControl Room Intake 175.11 -291.44 340 103.6 149 -1257.26 o524.02 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 -543156 -242.01 595 181 246 -538.59 -573.45 Unit 2 Main Steam Tunnel Unit 2 Combined Rx/Rw Vent -561.83 .-250.14 615 187 .246 -520.32 -565.32 Unit 2 Combined RxIRw Vent Unit2 PASS, -505.59 -424.24 660 201 230 -576.561-391.22 Unit 2 PASS Unit 2 Standby Gas -706.36 -375.58 800 244 242 -375.791-439.88 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 1 Main Stack Unit 1 Technical Support Center 212.12 -252.79 330 100.6 140 -966.80 -680.14 Unit 1 Technical Support Center Unit 1 Main Stack Unit 2 Control Room - West High 630.95 -386.65 740 225.6 121.5 -547.97 -813.99 Unit 2 Control Room - West High Unit 2 Control Room - West Low 626.66 -354.54 720 219.5 119.5 -552.26 -781.89 Unit.2 Control Room -West Low Unit 2 Control Room - East High 725.05 -338.09 800 2243.8 115 -453.87 -765.44 Unit 2 Control Room - East Highý Unit 2 Conrol Room - East Low 725,05 -33.09 800 243.8 115 -453.87 -765,44 Unit 2 Control Room - East Low C-,t 6'

r-Page.13 of 37

Calculation No: NMPAST-02-001 Constellation Rev*. 2 Nuclear Services Date: December 22, 2003 Table 7.1.2. Summary Table of Distances and Directions for:Various Releases to Unit 2 Control Room Intakes FROM &. (ft) Ay (ft) d Ax (ft) d (m) 10 (dOg)

Unit 1 Rx Bldg. Blowout Panel Unit 2 Control Room - West High 709.30 -289.97 766.28 233.56 112.24 Unit 2 Control Room - West Low .705.00 -257.86 750.68 228.8.1 110.09 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 -73.57 743.81 226.71 95.68 Unit 2 Control Room - East. High 838.56 -57.12'840.50 256.18 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 -240.54 240.72 73.37 182.23

-3 Unit 2 Control Room - West Low -13.67 -208.43 1208.88 63.67 183.75 ON Unit 2 Control Room - East High 84.72 -191.98 209.85 63.96 156.19 Unit-2 Control Room - East Low . 84.72 -191.98 209.85 63.96 15.6.19 Unit 2 Combined: RxdRw Vent Unit.2 Control Room - West High -27.65,-248.67.250.21 76.26 186.34 Unit 2 Control Room - West Low -31.94 -216.57 218;91 66.72 188.39 Unit,2 Control Room.-.East.High 66.45 -200.12 210.86 64.27, 161.63 Unit.2 Control Room - East Low 66.45 -200.12 210.86 64.27 161.63 Unit 2 PASS Unit.2 Control Room. - West High 28.60 -422.77 423.74 1291.5 176.13 Unit 2.0Cntrol Room - West Low 24.30 ;390.67 391.42 119.31 176.44 Unit 2 Control Room - East High 122.69 -374.22 393.81 120.03 161.85 Unit 2 Control Room - East. Low 1.22,69 -374.22 393.81 120.03 161M85 Unit.2 Standby Gas Unit 2 Control Room -,West High -172,17 -374.11 411.83 125.52 204.71 Unit 2 Control Room -.West Low -176,47 -342.00 384.85 117.30 207.29 Unit 2 Corntrol Room EastHigh -78.08 -325.55 334.79 102.04 193ý.49 Unit 2 Control Room - East LQw -78.08 -325.55 334.79 102.04 193.49 Page 14 of 37

SConstellaton Calculation No: NMPAST-02-001 C Rev. 2 Nuclear Services Date: December 22,'2003 Table 7.1.3. SummaryTable of Distances and Directions of Unit 2 Releases to the Unit 1 Technical Support Center FROM TO A x.(ft) I Ay (ft)I d(ft) - d(m),e0(deg)

Unit 2 Main Steam Tunnel Unit 1 Technical Support Center -428.21 -106.68 441.30 134.51 256.01 Unit 2 Combined RxIRw Vent Unit.1Technical Support Center -44648 -114.82 461.01 140U51 255.58 Unit 2 PASS. Unit.l Technical Support Center -390.24 -288.92 485.55 148.00 233A49 Unit2 Standby Gas Unit 1 Technical Support Center -591.01 -240.25 637.97 194.45 247.88 o(

I Page 15 of 37

SConstellation* Calculation No: NMPAST-02-001 oRev.2 Nu r Services Date: December 22, 2003 7.2. Building Wake Areas Due to the complexity of the geometry Of thestructural buildings for both Units 1 and 2, conservative building wake areas were calculated. The conservative assumptionsltaken to calculate the:wake areas are stated in 5 through 10 ,12 and 13 of Section 6.1. The calculations for determining building wake areas are as follows:

Unit 1 Releases to Unit 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 I Control Room Intake= 33 m- 2.1.95 m = 11 m.

One half east-west length of Unit 1 Turbine Generator Building = 0.5 x 99.67 m = 49.8m Wake Area for All Unit 1 Releases to: Unit 1 Control Room Intake = 11 m x 49.8 m = 550 m 2 Unit 1 Releases to Unit.2 Control Room 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 heightof Unit:2 Turbine Building = Height of Turbine Building - Max Height-of Control Room Intakes = 36.58 m - 16.1 m = 204 m North-south length of Unit 2 Turbine Building = 42.67 m Wake Area for All Unit 1 Releases to Unit2 Control Room Intakes = 20.4 m x.42.67 m =

870 m2 Unit 2 Releases to Unit 1 Control"Room Intakes (Excluding Unit 2 MaIn 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 height of Unit 2 Turbine Building = Height of Turbine Building - Height of Unit 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

Caiculation No: NM PAST-02-001 Rev. 2 Nuclear Services Date: December-22,2003 Wake Area for All Unit 2 Releases (Excluding Unit 2 Main.Stack) to Unit I Control Room Intakes= 14.6 m x 42.67 m = 623 m2 Unit;2 Releases to Unit I Technical Support Center(Excluding Unit,2 Main 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 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 MainrStack) to Unit I Technical Support Center = 30.18 m x 42.67 in = 1287 m2 Unit 2 Main Stack Release to Unit 1 Control Room Intake The Unit 2 Main Stack displacement fromt 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.

Effective height of Unit 2 Turbine Building = Height of.Turbine Building - Height of Unit I Control Room Intake = 36.58 m - 21.95 m = 146 m

.Effective height of Unit 2 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 Diameter of Unit 2 Reactor:Building = 2 x 26.06 m = 52.1 m 2

Wake Area of Unit 2 Turbine 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 = 1542 m 2 2 Wake Area for Unit 2 Main Stack Release to Unit 1 Control Room Intake = 623 m + 1542 m 2

2165 m Unit 2 Main Stack Release to Unit I Technical Support Center The Unit 2 Main Stack displacement fromrthe' Unit 2 Reactor and Turbine building is sufficient such that the building wake area for the Unit 2 Main Stack to the Unit 1 Technical Support Page 17 of 37

.11. ^ A-, ý7 Z_ ý A, A 17.1 Constellation NuOflS.rvjcE~s

.CalculationrNo: NMPAST-02-001 Rev. 2 Nuclear SerVICes .Date: December 22, 2003 Center includes both thetentire area of the Unit 2 Reactor Building and the north-south cross-sectional area 6f 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 Effective height of Unit"2 Reactor Building = Height of Reactor Building - Height .of Unit 1 Technical SupportCenter = 51.55 m - 6.4 m = 45.15 m North-south length of Unit 2 Turbine Building = 42.67 m Diameter of Unit 2 Reactor Building,= 2 x 26.06 m = 52.12 m 2

Wake Area of Unit 2 Turbine Building =30.18 m x 42.67 m = 1287 m :

Wake Area of Unit 2 Reactor Building = 45.15 m x 52.12 m= 2353 m2 2 2 WakeArea for Unit:2 Main Stack Release to Unit 1 Control:Room Intake = 1287 rn + 2353 .m

= 3639 m2 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

.assumed to+be the maximum of all four Control Room intakes.

Effective height of Unit 2 Reactor Building = Height.of Turbine Building- Max Height 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 System Building2 and Unit 2 Main Stack Releases to Unit 2 m = 1844 m Control Room Intakes = 35.4 m x:52.1 Unit 2 PASS Panel Vent Release to Unit,2 Control Room Intakes Per assumption 10 of Section 6.1i 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 = Height of 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

7t.

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22,2003 Wake Area for Unit 2 PASS Panel Vent Release to .Unit 2 Control Room. Intakes = 0.5 x 35.4 m2 x52.1 m= 922 m 2 Unit I Turbine Building Blowout Panel Release to Unit I Technical Support QCenter 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 1 Turbine Generator Building = Height of Turbine Building - Height of Unit 1 Technical Support Center = 33 m - 6.4 m = 26.6 mn.

North-south Length of the Unit 1 Turbine Building = 35.48 m Wake Area !for:Unit 1 Turbine Buildino Blowout Panel Release to Unit I Technical SuDDort Center = 26.6 m x 35.48 m = 943 m2 Table 7:2.1 summarizes the, building wake.areas calculated above.

Table 7.2.. CalculatedBUilding Wake Areas Release Intake Area (m2 )

Unit 1 -All Unit 1 CR 550 Unit l - Main Stack Unit ITSC 0.01]

Unit I - Reactor Building Blowout Panel Unit 1 - Turbine Building Blowout, Panel Unit 1 TSC 943 Unit I -All Unit2 CR-All 870 Unit 2 -All Except Main Stack Unit 1.CR 623 Unit 2 - All Except Main Stack Unitl TSC 1287 Unit 2- Main Stack, Unit : CR, 2165 Unit2 - Main Stack Unit 1 TSC 3639

.Unit 2'- Standby Gas Building Unit2 CR- All 1844 Unit 2- Main Stack Unit 2- PASS Panel Vent Unit 2 CR - All 922 Unit%2- Combined Radwaste/Reactor Building Vent Unit 2 CR.- All 0-01TT

,Unit 2 - Main Steam Tunnel

1. In accordance with assumptions 9 and 13 of.section 6. 1.

Page,19 of 37

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Servics Date: December 22, 2003 7.3. 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 greater than 2.5 times the height of adjacent buildings. Following this specification the Unit 1 stack release is clearly considered a grou nd-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 toý 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 in Section 6.

The diffuse area .source as described in the regulatory guidance (Ref. 5) was also. considered for the Unit 1 Turbine Building: and Reactor Building blowout panel release scenarios.

ARCON96 runs were performed using the diffuse.area source input for ARCON96 (as described in Ref., 5). The results suggest that the 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 for each release/receptor to be input as the direction from the intake to the releaSe.. To thispoint, 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, used instead of those provided in the ARCON96 ýuser'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 performed the input and output files have been provided on the enclosedCD. Appehdix C provides a list of computer runs and Appendix D provides a listing of all files on the enclosed CID.

Table 7.3.3-1 provides tabular results of the X/Q values for all releasestothe Unit I Control Room and Table 7.3.3-2 provides results of the XIQ values for all releases to the Unit 1 Technical Support Center- Table 7.3.4 provides tabular results of the 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

Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December,22, 2003 Table 7.3.1 ARCON96 Distances and Directions Input FROM TO Distance Direction (in) (degrees)

Unit 1 Control Room Intake Unit I Reactor Building Blowout Panel 103.6 329 Unit 1 Turbine Building Blowout Panel 71.9 297 Unit i Main Stack 121.9 346 Unit 2 Combined Fadwaste & Reactor 187 66

.Building Vent Unit 2 Main Steam Tunnel 181 66 Unit 2 Standby Gas Treatment System 244 62 Building Unit 2.Post Accident Sampling System 201 50 Panel Unit2 Main Stack- 413 53

.Unit 1 Technical SUpport Center Unit 1 Reactor Buildingý Blowout Panel 104.5 266 Unit 1 Turbine:Building Blowout Panel 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 76.01 Unit2 Standby Gas Treatment System 194.45 67.88 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 1 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- 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 256818 273.90 Unit 2 Control Room Intake West- High U.nit 1 Main Stack. 225.61 301.5

'Unit 2 Control. Room Intake West - Low 219.5 299.5 Unit 2 Control Room Intake East - High 243.8 295 Unit 2 Control Room Intake East - Low 243.8 295 Unit 2 Control Room Intake West.- High Unit 2 Combined Radwaste& Reactor 76.26 6.34

'.Unit 2 Control Room Intake West - Low Building Vent 66.72 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 3175 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 Unit 2 Control Room Intake West- Low Building 117.30 27.29 Page 21 of 37

Calculation No: NMPAST-02-001 Rev.2 Nuclear Services Constellation Date:. December 22,. 2003 FROM TO Distance Direction i(m). (degrees)

Unit 2 Control Room Intake East:'- HIgh 102.04 13.49 Unit 2 Control Room Intake East- Low 102.04 13;49 Unit.2 Control Room Intake West.- High Unit 2 Post AccidentSampling.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 'Cont*ol Room IntakeEast - Low 120.03 341.85!

Unit'2 Control Room Intake West - High Unit 2 Main Stack 286 45 Unit.2 Control Room Intake West - Low 280 45 Unit 2 Control Room. Intake East- High 257...... 22:5 Unit.2 Control Room Intake East - Low 258 22.5 Table 7.3.2. List of'Common/Default Input Data to ARCON96 Input Parameter Value Used Reference Lower Wind Measurement 9.45 rn Ref. 8 Height Upper Wind Measurement 60.66 m Ref. 8 Height Wind Speed Units .2 (mph) Ref. 26 Release Type. 1 (ground release) Assumption 11 Stack Velocity 0 Assumption 11

.Stack Flow 0 Assumption 11 Stack Radius, 0 Assumption 11 Elevation Difference 0 ýRef. 5 Surface Roughness 0.2 m Ref. 5

Wind Direction Window 90 degrees Code Default Minimum Wind Speed. 0.5 m/s Code Default Averaging Sector Width 4.3 Ref. 5 Constant Initial Diffusion Coefficients 0 Code Default Hours in Averages. see users guide (Ref. 2) Code Default

-Minimum Number of Hours see user's guide (Ref,.2) Code Default Expanded Output n Code Default Page 22 of 37

Calculation: No: NMPAST)02,-001 Constellation 'Rev. 2 Nuclear Services Date: December 22, 2003 Table 7.3.3-1. XIQ Values for the Unit I Control Room 3

XiQ Dispersion Coefficients (s / mr )

ReleasePoint 0-2 hrs 2-8 hrs 8-24 hrs -4 days,, 4-30 days U1 Reactor Bldg. Blowout Panel 4.82E-04 2.61 E-04 9.25E-05 6.70E-05 4.93E-05 Ul Turbine Bldg. Blowout Panel 1.03E-03 5,85E-04 2,07E-04 1.75E-04 1.52E-04 U1.MainStack 2.27E-04 1.26E-04 4.30E-05 3.58E-05 2.50E-05 U2. Combined Radwaste & Reactor Vent 1 77E-04 1.09E-04 3.92E-05 2.48E-05 1.85E-05 U2 Post Accident Sampling Sys. Panel 1.59E-04 1'.13E-04 4,19E-05 2.48E-05 2.OOE-05 U2 Standby Gas:Treatment Sys. Building 1.11 E-04 8;09E-05 2.91 E-05 1.82E-05 i.45E-05 U2 Main Steam Tunnel 1.90E-04 1.37E-04 4.93E-05 3.12E-05 2.56E-05 U2. Main Stack 4.18E-05 2.30E-05 8.994E-06 5.62E-06 4.31E-06 Table 7.3.3-2. X/Q Values for the Unit I Technical Support Center 3

X/Q Dispersion.Coefficients (s] m )

Release Point 0,2 hrs 2-8 hrs 8-24 hrs 1-4 days 4-30 days Uli Reactor Bldg. Blowout Panel 7.09E-04 5.60E-04 2.34E-04 1.71 E-04 1.41E-04 U1 Turbine Bldg. Blowout Panel 5.91 E-04 4.26E-04 1.63E-04 1..35E-04 1.16E-04 Ut Main Stack 3.47E-04 2A2E-04 8.22E-05 6.06E-05 5.OOE-05 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 162E-04 1*19E-04 4.28E-05 2.72E-05 2.24E-05 U2 Main Steam Tunnel 3,27E-04 :2.41 E-04 8.;38E-05 5.95E-05 4.76E-05 U2 Main .Stack 4.95E-05, 2.69E-05 1.603E&05 6.67E-06 4.85E-06 Page 23 of 37

Calculation No; NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003 Table 7.3.4. XIQ Values for the Unit 2 Control Room U2 Control Roomlntake - Upper West U2 Control Room Intake - Upper East X/QDispersion Coefficients (s I m3 XJQ Dispersion:Coefficients (s/Im, Release Point 0-2 hrs 24 hrs 8-24 hrss 1-4 days 4-30 days 0-2 hrs 2-8 hrs 8,24 hrs 1-4 days 4-30 days U1 I0eactor Bldg. Blowout Panel I.23E-04 7.21E-05 2.57E-05 2.28E-05 2.05E-05 1.06E-04 6.70E-05 2339E-05 2.17&-05 1.96E-05 U1 jurbneBldg*.Blowout Panel 1.30E-04 9.03E-05 3A.45E-05 2;925&05 2.56E-05 1.09E-04. 7..73E-05 2.95E-05 2.45E-05 2.14E-05 Ul INlain Stack 11.06E-04 5.90E-05 2.23E-05 1.73E-05 11.43E-05 9.83E-05 5.81 E-05 2.22E-05 1.83E-05 1.57E-05 U2 Combined Radwaste & Reactr Vent 8.24M-04 6.29E-04 2.28E-04 56E-04 i.26E-04

,1 1.09E-03 7.23E-04 12.46E-04 t 922-04 1.47E-04 U2 Post Accident Sampling Sys. Panel 3.36E-04 2.OOE-04 7.31 E-05 5.53E-05 4.04E-05 3.74E-04 2,05E-04 7.08E-05 5.41E-05 3.88E-05 U2 Standby Gas TreatmentSys. Building 3.625-04 2.59E-04 9.48E-05 6,16E-05 4.42E-05 5.31 E-04 3.70E-04 1.35E-04 9.16E-05 6.70E-:05 U2 Main Steam Tunnel 1.13E-03 7.49E-04 2.76E-04 1.90E-04 1.49E-04 1.47E-03 8.80E-04 3.32E-04 2.26E-04 1.68E-04 U2 Main Stack 7.04E-05 3.95E-05 I .49E-05 9.96E-06 7,46E-06 1 8.03E-05 4,483-05 1.68E-05 1.20E-05 8,83E-06

U2 Control Room Intake - Lower West U2 Control Room Intake -Lower East r

____Di_______________________ ( 1M 3 X/ODispersion Coefficients (s im.

Release Point 0.2hrs 248 hrs 8-24 hrs 1-4 days 4-30 days 0-2 hrs 2-8 hrs 8-24 hrs 1-4 days 4-30 days UI Reactor Bldg. Blowout Panel 1.26E-04 7.,73E-05 2.74E-05 2.45E-05 2.23E-05 1.06E-04 6.68E-05 2.39E-05 2.16E-05 1.95E-05 Ul Turbine Bldg. Blowout Panel 1.31E-04 9.42E-05 3.59E-05 3.01E-05 2.63E-05 1.08E-04 7.69E-05 2.96E-05 2.44E-05 2.14E-05 Ut Main Stack 1.102-04 6.116E-05 2.31Eý05 1.85E-05 1.54E-05 9.54E-05 5,68E-05 2.15E-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 9.43E-04 6.34E-04 2.132-04 1.67E-04 1.295-04 U2 Post Accident Sampling Sys. Panel 3.84E-04 2.282-04 8.235-05 6.28E-05 4.57E-05 3.672-04 2;01 E-04 6.952-05 5.32-E05 3.83E-05 U2 Standby Gas Treatment Sys.-Buildin 4.05E-04 2.95E-04 1.08E-04 6.98E-05 .00E-05 5.33E-04 3.72E-04 1.36&-04 9.17E-05 6.72E-05 U2 Main Steam Tunnel 1.468-031 9.74E-04 3.63E-04 2.452-04 1.90E204 1.46E-03 8.70E-041 3.32E-04 2.23E.04 1.68E-04 U2 Main Stack 7.152-05 4.012 -05 1 1IE05 7.55E 06 7.78E-05 4.312-05 1.64E-05 1.16E-05 8.615-06

-I Page.24 of 37

' 'Calculation No: NMPAST-02-001 Constelation.. Rev. 2 NulearServices Date: December 22, 2003

8. Conclusions Atmospheric dispersion coefficients (X/Q) values.,have been calculated at-the control room intakes at.both Units. 1 and 2 and the Unit I Technical Support Center due to all postulated

releasescenarios. Tables 7.3.3-1. 7.3.3-2 and 7.3.4. provide conservative XIQ values for the scenarios listed above.

9. References

1. NMP Purchase Order, No. 02-40502, May 22, 2002.

2. NUREGICR-6331, "Atmospheric.Relative Concentrations in Building Wakes," May 1997T.

3. Regulatory Guide 1.145, Rev. 1, "Atmospheric.Dispersion Models for Potential Accident Consequence Assessments-at Nuclear Power Plants," February 1983.

4. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluation Design Basis. Accidents at Nuclear Power Reactors," July*2000.

5. Draft Regulatory Guide DG-1 111 and Regulatory Guide 1_.194, "Atmospheric Relative Concentrations for Control. Room Radiological Habitability Assessments at Nuclear Power Plants," UQ.S. NRC Office of Nuclear Regulatory. Research, December 2001. and June 2003.

6. CNS ARCON96 ComputerCode Verification, Rev. 1, June 24., 2002.

7. CNS Quality Assurance Program, Rev. 4, December 1,.2002.

8. E-mail Ltr. from Thomas Galletta (NMP) to James Heffner (CNS), 5/24/2002, "Re: MET Data".

9. E-mailLtr. from Thomas Galletta (NMP) to Shane Gardner (CNS) ,4/24/2002, "NMP ARCON96: Met Data - No Tabs".

10._ NMP Unit 1 Drawing, C-18713-C, Sht. 2,;- Rev. 9, 522174.

11. NMP Unit 2 Drawing, EA-IA-7, Rev. 7, 5/31/83.

12. NMP Unit 2 Drawing, EA-3A-4, Rev. 4., 5/4/88.

13. NMP Unit 2 Drawing, ES-52A-7, Rev.7, 11/24/82

14. NMP Unit 2 USAR Figure 1.2-11, Sht. 2, Rev.. 0, April '1989.

15. NMP Unit 1 UFSAR, Rev. 15, November 1997.

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 RoomAir Intake and Emergency Operations Facility for All NMP Unit 2 Release-Building Scenarios."

18. MES :Calculation, 8/7/90, "Accident X/Q Values for Nine.Mile Point Unit 1 Releases from the Main Stack and the Reactor Buildings."

19. NMP Unit 2 USAR, Rev. 14, February 2001.

20. NMP Unit 2 Drawing, EV-202E-2, Rev. 2, 3/23/84.

21. NMP Unit 2 Drawing, EA-56B-5, Rev. 5, 5/31/83.

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, C-1 8717-C, Rev 21, 6/19/01.

Page 25 of 37

0 q19 Constellation .. Calculation No:. NMPAST-02-O01

aRev. 2 Nuclear.;rvices Date: December 22, 2003

25. NMP Unit 2 Drawing, EA-41A-6, Rev. 6, 4/30/91.

26. E-mail Ltr. From Thomas Galletta (NMP) to Shane Gardner (CNS), 7123/02, '5 year JFD's".

27. E-mail Ltr. From Thomas Galletta (NM P) to Shane Gardner (CNS),: 8/1/02, "ARCON96

'Data - Rev. 1".

28. CNS Calculation No. NMPAST-01-001, "Calculation of X/Qs at the EAB and LPZ from Releases at NMP Units I -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

LIC-0 1(o Calculatiori No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22,2003 Appendices 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

Calculation. No: NMPASTL02-001 Rev. 2 Nuclear Services:

Constellation Date: December 22, 2003 AppendixA - Site Plan Showing Associated XIQ Directions NW NNW N Page 28 of 37

z.1 .. . Calculation No: NMPAST-02.001 Nuclear Services Date: December22,Rev.

20032 Appendix B - Representative ARCON96 Input File The following lisa copy of the:ARCON96 input file for the Unit I Main Stack release tothe Unit 1 Control Room intake. Additional input files are provided on the attached disk.

1 C:\NMP CR XO\NMP RI.MET 9.45

.60 .66 2

01,.70

.55~0 .oo0 0.00O 0.00 346 90 121.90 21... 95 0".00 u1MS_TU1.log UIMS _U.CFD

.2 0.*50 2 '2 4 8 12 24 96 168 360 720 1 2 4 8 12 22 87 152 324 648 0.00 o0.00 n.

Page 29 of 37

Calculation No: NMPAST-02,401 Constellation Rev. 2 Nuclear Services Date: December 2, 2003 Appendix C - List of Computer Runs The ARCON96,computer run identifier and corresponding release/intake scenario are summarized in the list below. The computer run identifier, in conjunction with the appropriate file extension, defines the input and output files for each run. The ARCON96 input file extension is ".RSF" and theoutput 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 Intake U2STG U2UW Unit 2 Standby Gas Treatment Unit 2 CR - UpperWest U2STG U2UE .ystem.Build.ing Unit 2 CR- UpperEast U2STG U2LW Unit.2 CR - Lower West U2STG U2LE Unit 2 CR - Lower East

U2STG UI Unit:1 CR "U2STG U1TSC Unit 1 TSC

" U2PASSV U2UW Unit 2 Post Accident Sampling Unit 2 CR - Upper West U2PASSV U2UE System Panel Unit 2 CR - Upper East U2PASSV.U2LW Unit 2 CR - Lower West

'U2PASSV U2LE Unit 2 CR - Lower East U2PASSV Ul .Unit 1 CR U2PASSV UITSC Unit 1 TSC U2MST U2UW Unit.2 Main Steam Tunnel Unit 2 CR - Upper West U2MST U2UE Unit 2 CR - Upper.East U2MS,.T U2LW Unit 2 CR - LoWer West U2MST U2LE. Unit 2 CR.- Lower East U2MST Ul Unit. 1.CR U2MST U1TSC 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 - LowerEast U2MS UI Unit 1 CR U2MS UITSC Unit I TSC U2CRRV, U2UW Unit 2 Combined Radwaste & Unit 2 CR - UpperrWest WU2CRRV U2UE Reactor Building Vent Unit.2 CR - Upper East U2CRRV U2LW Unit: 2 CR- Lower West U2CRRV U2LE Unit 2CR- Lower East.

U2CRRV Ul Unit 1 CR U2CRRV UITSC Unit I TSC UT. U2UW Unit I Turbine Building Blowout Unit 2 CR - Upper West UIT U2UE Panel Unit2CR -UpperEast U1T U2LW Unit .2 CR - Lower West U.T U2LE Unit 2.CR- Lower East UlT UI Unit 1 CR UIT UITSC Unit 1 TSC

.U1 R U2UW Unit 1 Reactor Building Blowout Unit 2 CR - Upper West UIR U2UE Panel Unit2 CR- Upper East U1R U2LW Unit 2 CR - Lower West UIR U2LE Unit 2.CR - Lower East Page 30 of 37

Calculation No: .NMPAST-024001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003

.Computer Run. Identifier Release Intake U1R Ul Unit A CR UIR UITSC Unit 1 TSC U1MS U2UW Unit 1 Main.stack Unit 2CR - Upper West UIMS U2UE Unit2 CR-Upper East:

UIMS U2LW Unit 2CR- Lower West UIMS U2LE Unit 2CR- Lower East UI uI

_MS Unit I'CR UIMS. UITSC Unit: 1 TSC Page 31 of 37

CalculationNo: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003 Appendix, D - List of Files, On CDROM Note:. This directory listing does not include the calculation document, cover pageý and review checklist files.

DireCLory of D:\

12/22/2603 05:02 PM <DIR>

12/22/2003 05:02 PM <DIR>

09/09/2002 02;42 PM. 20,G72 Distances Calculations.xls 12/22/2003 03:15 PM <DIR> Inputs and.,0utputs.

08/02/2002 10-:5.6 AM 1,621,486 NMP_.RI.MET 12/22/2003 03:'0,74PM 30,208 Results Summary (MET DATA Rev 1).xls 1:1/18/2003 ,02;27 PM: <DIR> SCOPINC

6. File(s) 4,359,152 bytes Directory of D:\Inputs and, oUtputs 12/22/2003 0.3:: 15 PM <DIR>

12/22/2003 i s .Pm <DIR>

12/22/2003 12 AM 1,544 run.revision2.bat 11/18/2003 02: 27 PM <DIR> UNIT1 02:

27 PM <DIR> UNITI-TSC 12/22/2003 08 - 05 AM <DIR> UNIT2 1 Pi'le (s) 1,544 bytes Directory of D':\Inputs and 0utputs\UlNIT1 11/18/2003 02:27 PM <DIR>

11/18/2003 02:27 PM.

.05/09/i197 03:00 PM 14,620 ARCHELP.TXT 06/27/1997 12:41 PM 380,92A ARCON96F.RXE

ý05/09/1997 *03:00 PýM 43,612 'ARCONVB2..EXE 12/22/2003 03:09 PM CFD 01/11/1994: 12:00 AM 3 93,942 DOSXMSF.EXE 12/22/200.3 03.*I. PM. log 01:21 PM 07/29/2002 ,545 run allrelease ulcr,.bat:

12/22/2003. 01:57 PM 401 U1MSU1.RSF 12/22/2003 :01:57 PM 381 UIT UI.RSF 12/22/2003 01:57 PM 12/22/2003 01:57 PM 387 U2CRRV U1.RSF 12/22/20'03 '01:57 PM 385 U2MSTU:.,RSF 12/22/2003, 01:57 PM ,383 U2MS U1.RSF 12/22/2003 061:57 PM ,389 U2PA~ssv U1.RSV 12/22/2003 01.57 PM. 385.U2STGUl.RSF 13 File(s) 936,739 bytes Diirectory of D:\Inphuts and. Output\AUNITI\CFD 12/22/2003 03:09 PM <DIR>

12/22/2003 03:09 PM <DIR>

12/22/2003 02: 53 PM 11,168 DIMS....CFD 12/22/2003 02: 53 PM 11,168 U1R U1.CFD 12/22/2003 02.: 53 PM 11,168 UIT UL. CFD 12/-22/2003 02: 5:3 PM 11,168 U2CRRV_UI.CFD 12/22/2 003 02: 53 PM U2MSTU1.C-FD 12/22/2003 02:.53 PM 11,168 M2MS_61.CFD 12/22/2003 .02: 53 PM 11,168 U2PASSV U1.CFD 12/22/2003 02: 53 PM '11,168 U2STGU1,CFD Page 32 of 37

VVIzLCA:1I 4-c Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December,22, 2003 8' File(s) 89,344 bytes Directory of D.:\Inputs and 0utputsk\uNITl\10g

12/22/2003 03': 11 PM <DIR>

12/22/2003 03:11 PM <DIR>

12/22/'2003 02:53 ,PM 4,838 UlMS_UI.l1og 02:53 PM* 4,838 UIRU.l*og 12/22/2003

12/22/2003 02.:53 PM 4,838 UIT .Ul.log 12/2212003 02:r53 PM 4,838 U2CRRVU1.10g 12/22/2003 02:53 PM 4,838, U2MSTUI.1og 12/22/2003 02:53 PM 4,838 U2MSUl.log 12/22/2003 02:53 PM" 4,838 U2PASSV_Ul.log 12/2 2/2 003 02:53 PM, 4,838: U2STG_Ul.log 8 File(s) 38,704 bytes[

Directory f6ED:\Inputs and Outputs\UNITI-TSC 11/18/2003 02:27 'PM <DIR>

11/18/2003 02.::27 PM <DIR>

05/09/1997 03:00 PM 14,620 ARCHELP;TXT 06/27/1997 380,928 ARCON96F..EXE 12' 41 PM 05/09/1997 03:o00 PM' 143,612 ARCONVB2..EXE 12/22/2003 031:11 PM <DIR> cFD 01/11/1994 1:21:0:0 AM 393,942 DOSXMSF.EXE 12/22/2003 03:11 PM <DIR> log 09/09/2002 01:09 PM 617 run. allrelease ultsc.bat

.09/09/2002 01:06 PM 407 UIMSUITSC.RSF

.09/09/2002 01:24 PM 387 UIR UITSC.RSF 09/09/20012 01:06 PM 387 DUITVITSC.RSF 09/09,/2002 01:06 PM 393 U2CRRVUITSC.RSF 01: 06 PM 391 U2MST UITSC.RSF 12/22 /2 003 389 U2MS UITSC.RSF 08: 09 -AM

.09/09/2002 .01:"06 01:06

~'I

. 395 U2PASSV_U 1TSC.RSF 0'9/09/2002 PM' 391 U2STGU1TSC.RSF 13 File(s) .936,859 bytes Directory of D:\Inputs and 0utputs\LTIT1-TSC\CFD 12/22/2003 03:11 PM <DIR>

12/22,/20.03 03:11 PM <DIR>

09/09/2002 01:09 PM 11,166 UIMSU1TSC.CFD

09/09/2002 01:09 PM 11,168 UiRUl1TSCTSC.CFD 09/09./2002 01:09 PM 11,1686 UIT U1TSC.CFD.

09/09:/20 02 .01:09 PM 11,168 U2CRRV_UITSC.CFD 09/09/20 02: 61:09.PM' 11,16 DU2MST__UTSC.CFD 12/22/2003 .02:53 PM 11,168 U2MS_U1TSC.CFD 09/09/2002 01.: 09 PM 11,168 U2PASSV UITSC,CFD "09/09/2002* 01:09 PM 11,168 U2STG"UITSC..CFD 8 File(s) 09,344 bytes Directory of D;\Inputa and Outputs\UNITI TSC\log 12/22/2003. 03: 1i PM <DIR>

12/220/2003 03: 11 PM <DIR>

09/09/2002 01: 09 PM 4,838 UIMS_U1ITSC.log 09/09/2002 01:09 PM UIR_UlTSCTSC.iog 4,838 00/09J2002o 01;:09 PM UIT__UITSC.109 09/09/2002 01: 09 PM ,U2CRRVU!TSC.lQg 4,838 4,83"8 U2MSTUITSC log 09/09/2002 01:09 PM

.12/22/2003 02:'53 PM U2MS_UITSC.1og Page.33 of 37

v~ikC4,- --4) CalcUlation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December 22, 2003 09/09/2002 01.:09 .PM 4,838 U2PASSV_U1TSC.Iog 09/0,9/2002 01 09 PM ,4,838 U*STGU1TSCc-o9

'8 File(s) 38,704 bytes.

Directory of D,: \,Iriuts and Ou~tputa4\LNIT2 12/22/2003 08:05 AM <DIR>

12/22/2003 08:05 AM. <DIR>

05/09/1997 03: 00 PM 14,620 ARCHELP.TXT 06/2.7/1997 12:41 PM. 3 880:, 928 ARCON96F.,EXE 05/09/1997 03.: 00 PM 143,612 ARCoNVB2..EXE 12/22/2003 03:10 PM <DIR> CFD 01/11/1994 12: 00 AM 3 93,942 DOSXMSF.EXE 12/22/2003 03 :12 PM <DIR> 1-09 07/2,9/2002 01: 20 PM 2,128' run allrelease u2cr..bat 09/09/2002 01 ,06 PM 387 U1MSU2LE.RSF-09/09/.2.002 01:06 PM 387 UIMSU2LW..RSF 09/0.9/2002 01:06 PM' ,3'87 t1MSU2UE. RSF 09/09/:20.02 01-06 PM 387 UIIMSU2UW.RSF 09/09/2002 01:06 PM 385 UIR U2LZ.RSF 09/ 09/2002 01.:06 PM ,385. UIRU2LW.RSF 09/09/2002 01.:06 PM 385 UIR--U2UFý.SF 09/0.9/2:002 01:06 PM 385 U1R.U2UW.RSF 01:06 PM 385 UiTU2LE.RSF

.0 /09/2002 09/09/2002 01:06 PM 385 UIT _U2LW.RSF 09/09/2002 01:06 PM 385.UlTU2UE.RST 09/09/2002 01:06 PM 385 UIT U2UW:RSF 09/09/2002 01:06 PM 391 U2CRRV U2LE.RSF 09/09/2002 0,1:06 PM 391 U2CRRV U2LW RSF 09/09/2002 01:06 PM ,391 U2CRRV-U2UE.RSF 09/09/2002 01:06 PM. 3"91 U2CRRV U2UW.RSF 09/09/2002 01:06 APM 389 U2MST UJ2LE.RSF 09/09/2002 01:06 PM 3.89 U2MSTTJU2LW. RSF 09/09/2002 0.1:06 PM 389 U2MST U2UE.RsF 12/22/2003 010:06 PM 389 UM2NST-2tltW.u RSF.

12/22/2003 08.:,09 AM .387 Ut2MSU2LE.RSF 12/22/2003 08:09 387 U2MS._U2LW.RSF 12/22/2003 o0: 09 AM 387 U2MS U2UE.RSF 12/22/2003 08.09 387 M2MS U2UW.RSF 12/22/2003 08-.09 393 U2PASSVU2LE.RSF 08! ,09 AM 393 U2PASSV U2LW.RSF 12/22/2003 08:009 AM '393 U2VACSVU2UE.R8F AM 393 U2PASSV U2UW.RSF 12/22/2003 ý08:09 AM 12/22/2003 008;09 389 U2STG U2LE.RSF AM 08:09 389 U2STGU2LW.RSF

,12/22/200.3 AM

12/22/2003 08ý:09 3,89 U2STG.U2UE.RSF 08:09 389' V2STGU2UW,.RSF.

37 Pile(s) 947,654 bytea Directory of D. \Inputs and Outputs\UNIT2\CFD

12/22/2003 03:10 PM, <DI'R.

03,:10 PM <DIR>

12/22/2003 01:

01: 10lo 09/09/2002 PM 11,168 U1M8_U2LR.CFD 09/09/2002 01:10 PM ,168: qiNS_L2Lw.CFD 01,:10

.09/09/2002 PM 11,168 HIJMSU2URECPD 09/09/2002 01-: 10 PM U1MSULTJW.CFD 11 .168. UlR_52 I.R.C-F1

09/09/2002 01,10 PM 01: 10 11,168 !J1RU2LW-CFD

09/09/2002 PM 09/09/2002 01 10 PM (nitU2LTJ. CFD 09/09/2002 01:10 PM; 11,168 WiRU2UW.CFD Page 34 Of 37

ýV noC 1( -ý4 Calculation No: NMPAST-02-001

constelatien Rev. 2 Nuclear Services Date: December 22, 2003 09/09/2002 01:10 PM 11,168 UIT U2LE.CFD

.09/09/2002 0i:10 ýPM 11,168 U$T _2LW:..CFD 09/09/2002 01':10 PM 11,168 U1T7U2UE.CFD 09/09/2002 01:10 PM 11,168 U1T'_U2UW.CFD o9'/0o/2o02 09/09j/2002 01:.10 ýPM 11,168 U2CRRVU2LE.CFD 01:10 PM 11, 16 U2 CRRV.U2LW. CF 09/09/2002 01:10 PM 11,168 U2CRRV U2UE.CFD 09/09/2002 01Oi-0 PM .14,168 U2CRRV U2LW.CFD 09/09/200 2 01:10 PM 11,168 U2MSTU2LE.CFD "09/09/2002 ,01:10 PM I1, 168 U2MST.U2UW.CFD 09/,09/2002 .01:10 PM 11,168 U2MST U2UE.CFD 09/09/2002 01: 10 PM 12/22/2003 02:53 PM .11,168 U2MSTU2LW.CFD 12/22/2003 02:53 PM. 11,168 U2MS U2UE.CFD 12/22/2003 02:!53PM :11i168 U2MSU2UW.CFD 12/22/2100,3 02:,53 PM 12/22/2003 02:53 PM .11,168 11,168 U.2 PSVU2.LW.CFD U2PANSVU2LE.CFD 12/22/2003. 02:53 PM, 11,168 U2PASSV U2UE. CFD 12/22/2003 02:53 PM 11 ,68 U2PASSV U2LW.CFD 12/22/2003 02:53 PM 12/22/2003 02:53 PM 11,168. USTbU2LE.CFD) 12/22/2003 02:53 PM ' 11,168 U2STG._U2LW.CFD 12/22/2003 02:53 PM 11,168 U2STGU2UE.CFD

.. 12/22/2003 02:53 PM 11, 168 .U2STGCU2UW.CFD 32 File(s) 357,376 bytes Directory ofD:\Inputs. and Outputs\UNIT2\log 12/22/2003 03:12 PM <DIR>

12/22/2003 03: 12 PM <DIR>

09/09/2002 .01: 10. PM 4,838 UIMS_U2LE.lo9

,09/09/2002. PM 4,838 UIMS_U2LW. ,log 09/09,/2002 01.10 PM 4' 838 UIMS U2UE. log 4,838 UiMS-U2UW.

09/09/2002 01:1:0 PM log 09/09/2002 .01: 10 PM ul Rý_U2L.. log 09/09/2002 01:10 PM 4,838 Di R_2LW. log 09/09/2002 PM D~l 2 *2UE. 10lo 09/09/2002 *01:

01':10 10 PM 4., 8 381 DiR_U2UW.loy 4,838 09/09/2002 01: 10 PM UIT_U2LE1o0g 09/09/2002 PM 4,838 UITU2LW. log 09/109)I2002, 01-:10 PM 4,838 UlTU2WE. log 01:10 09/09/2002. PM 4,838 DITIMU2W. log 09/09/2002 01:10 PM 4, 838 U2CRRVU2LtE. iog' 09/09/20.02 01: 10 PM 4, 838 u2CRRVU2LW.. log 09/09/2002 01: i0 PM 4,838 U2CRRV U2UE. log 01.: 10 PM 4,83. U2CRRVU2tN. log 09/09/2002 PM 4,838 U*MST__U2LE. log 09/09/2002 01 :10 PM 4, 838 .U2MSTu2LW-. lo1 09/09/2002 PM 4,838- U2MST,2U2.log 01:10 U2MSTU2UW.log 19/b9/2002 PM 92/22/2003 02: 53 PM 4,838 U2MS u2L,. log 12/22/2003 02:53 PM 4, 838 U2MS t2LW. 1og 12/22/2003 02: 53 PM 4,838 U2MSU2UE -log 12/22/2003 02:53 PM 4,838 U2MStU2UW. log 12/22/2603 02:53- PM 4,838 U2P!flSV U2LE.1oq

.02: 53' PM 4,838 U2 PASSVU2LEW. log 12/22/21003 12/22/2003 02: 53 PM 4,838 U2PASSVU2UE.log 12/22/2 003 02 :53 Pm 4,838 U2 PASSV_2UW. log 4*,838 02:53 PM 4,838 U2STG. U2LE.1og 12/22/2 003 PIM a2STGeU2LW.7og 12/22/M03 U2STGU2tJE.log 02 :53 PM Page 35 of 37

,AVC*? (.-ý 0 Calculation No: NMPAST-02-001 Constellation Rev. 2 Nuclear Services Date: December22, 2003 12/22/200.3 *02:53 PM 4,838 U2STGU2UW..log 32 File(s) 154,816 bytes Direcqtory of D.:\SCOPING 11/18/2003 02:27 PM <DIR>

11/18/2003 02:27 PM <DIR>

11/18/2003 02:127 PM <DIR> Diffuse Sdurde 0 File(s) 0 bytes Directory of D:.\SCOPING\biffuse Source 11/18/2003 02:27 PM <DIR>

11/18/2003 02:27 PM <DIR>.

.11/18/2003 02.:27 PM .<DIR> UNIT 1 11/48/2003 02:27. PM <DIR> UNIT 2 0 File(s) 0 bytes Directory of D:\SCOPING\Diffuse Source\uNIT 1 11/18/2003 02:27 PM <DIR>

11/18/2003 02.:27 PM <DIR>

06/27/1997 12:41 PM 3804,928 ARCON96F.EXE 12/22/2003 03:10 PM. <DIR> CFD 12/22/2003 ,03:12 PM ,<DIR> log 09/09/2002 01:28, PM 348 run_allreleaseulcr.bat:

09/09/2002 01:26 PM 393 U1RU1TSCDS.RSF 12/22/2003, .01:57 PM 3.87 U1RU1 DS.RSF 09/09,/2002 01:2 6 PM 393 UlT U1TSC DS.RSF 12/22/2003 01:57 PM 387 UlT-U1 DS.RSF 6 File(s,) 382,836 bytes Directory of D:\SCOPING\Diffuse:Source\tINIT I\CFD 12/22/2003 03: 10 PM <DIR>

12/22/2003: 03: 10 PM <DIR>

09/09/2002 01: .28 PM 11,16.8.U!R_U1TSCDS.CFD 12/22/200'3 02: 53, PM 11,168 U.R_U1 DS-,CFD 09/09/2002 01: 28 PM 11.,168 UITU1TSCDS.CFD 12/22

?/2,003' 02: 53 PM £1,16.8 Ul.TUlDS.CFD 4 File(s) 44,672 1bytes Directory of. D: \SCOPING\Diffuse Source\*UNiT 1\log

,121227/2003 .03:12, PM <DIR>,

12/22/2003 03:12 PM <DIR>

09/09/2002 M0:28 PM 4,838 U1R U1TSC DS.1o0 12/22/2003: 02:53 PM 488U1R_U1_DS.log 09/09/2002 01:28 PM 4,o838 UlT_UITSCDS.log 12/22/2003 02:53 PM '4,838 UIT Ut1DS.lo<

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90 42kC-749( - ý Calculation No: NMPAST-02-001 Rev.

2 Nuclear Services Constellation Date: December 22, 2003 09/09/2002 01:12 PM 391 U1R U2LWDS.RSF 09/09/2002 01'12 PM ý391 U!lRU2UE. DS.RSF 09/09/2002 01:12 PM 391 MiR U2UN DS.RSF

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~NIS CORPORATION YS NISYS-11 69-DV001/R0 Nine Mile Point Nuclear Station 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 30096-161.9 Prepared for Nine Mile Point Nuclear Station, LLC Lycoming, NY

08/25/2003 18: 11 61.64663408 T PAGE 61 Aug-.2S-03 VY:0O8 N.ISYS Ccvpoi'-otic-io 770 497 8e42. P. *z Nine Midt ftor' Nu4.car Scation NIS YS NUPAST-01-OO2 and NMPAST-42-OO1 COMPORATHIN"

-N1SYS-1369.UVou1Ano APPROVALS z4kolu 6/2 5/C3 Prepared by Duar~e T.. Nak~hat, PhO. PE Date F46V "1d by T. MA. Carroll / ~te

&4~sJo 3 Approwo~ by John P. Nurhamn, PE: Date 0 initial Issue, Pages2 4f.12

Nine Mile PointNuclear Station Designi Verifilcaion of Calculations NMPAST-O1-O1 and NMPAST-02-001 VNIS YS Cowrot fTION NISYS-1 1690-DVOO1/O APPROVALS Prepared by Duane T. Nakahata, PhD,. PE Dato R6iewed by T. M. Carroll " Elate Approved by John P. Durham, PE Date Revision Histo 4Y Revisionq Summary of Change(s)

Level 0 Initial Issue Page 2 of 12

914 Nine Mile Point NuclearStation Design Verification of Calculations NM1AST-Ol-OQl and NMPAST-02-001 NIS YS C.ORP'ORATION NISYS-1169-DVOO1IRO Table of Contents OBJECTIV E ................... ................................ ,.............. w................. ,.................................. 4 1.0 OBJECTIV............................. ..............

2.0 METHOD AND EXTENT OF DESIGN VERIFICATION............. .. .. 5

3.0 REFERENCES

I 6 4.0 RESULTS .......................................................................................................................... 7 5.0 RECOMMENDATIONS ..................... . .. .....................

. .... 12 ATTACHMENTS 1 Design Verification Criteria (NMPAST-01 -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-ofCalculations NIS YS NMPAST-O!.O-i and NMPAST-02-001, NISYS-1169-DV'01IRO 1,0 OBJECTIVE The. objective of this report is to perform a design verification of. Nine: Mile Point Nuclear Station (NMP) calculations NMPAST-01-001, Rev. 1 (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 excilusion area boundary (EAB) and low population zone (LPZ) boundary, due to ýreleases from specified Unit 1 :and Unit 2 sources. Calculation NMPAST-02-001 uses the 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 ar~e needed to perform Alternative Source Term scoping calculations, which are, documented elsewhere.

Page 4.of 12

ccý ri 6 - 9.4.

Nine Mile Polmt Nuclear Station Design Verification of Calculations NMPAST-01-01 and NMPAST-02-001 OC ORAPO!ION NISYS-1169-DVOO1/RO 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 -001 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 will be 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 design verification criteria sheets as required by Reference 6 areprovided as Attachments 1 and

2. As required by Reference 7, a Certificate of Conformance,. signed by NISYS Corporation's Quality Assurance Manager is provided as Attachment 3.

Page 5 of 12

Nine Mile Point Nuclear Station NY Design Verification of Calculations- NISYS NMPAST-01 -001 and NMPAST-02-001 CORlPORATION NISYS-1169-DV001/H0

3.0 REFERENCES

1. Calculation NMPAST-01-001, Revision 1, Calculation of X/Qs at the EAB and LPZfrom Releases at NMP Units I and 2.

2. Calculation NMPAST-02-001, 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, RSICG Computer Code Collection - ARCON96, NUREG/CR-6331, Revision 1 (May 1997), Atmospheric Relative Concentrations in Building Wakes.

5. Nine Mile Point Procedure NEP-DES-07, Revision 4, Design Verification.

6, NISYS Corporation Project Instruction, NISYS- 1169-PI001/RO, Performing Design Verification of Atmospheric Dispersion Calculations.

7. Nine Mile Point Purchase Order No. 03-45612, independent Verification of Calculations NMPAST-01 -001 and NMPAST-02-001,, dated 7/112003.

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.ýS. 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), CD-R compact disc containing computer files for NMPAST-01-001, Revision 1.

11. NMPAST-02-001,-CD (916/2002), 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 USAIR Figure 111-10, Revision 14 (June 1996), Reactor Building and Turbine Building Cross-Section.

Page 6 of 12

Nine Mitle Point Nuclear Station N Y NMPAST-O!-O01 anrd NMVPASIT-02401 CO*JPORATjI)v NISYS- 1169-DVOO1RO 4.0 RESULTS Design Verification Checklist Document: NMPAST-01 -001. Rev. 1, Calculation of X/Qs 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 RevIewCeckA

YesI NoJWA

1. Were the Inputs correctly selected? X la. In.NMPAST-o1-oo1, 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 (1.9 and 1.6 km for Units. 1 and 2, respectively for the Esector), rather than to the eastern boundary of the NMP site (approximately 0.7 kmrfor Unit I (Ref. 12)).

Per IOCFRIO0.3, 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, or 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 theý highway, railroad, or waterway, in case of emergency, to protect. the.public health and safety. Residence within the exclusion area shall normally, be prohibited. In any event, residents.shall be subject to ready removal in case of necessity. Activities unrelated to operation of the. reactor may be permitted in an exclusion area .under appropriate limitations, provided that no significant hazards.to the public health and safety will result."

1b. Although the values used for design inputs are referenced (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. Altematively, it is recommended that the appropriate figures from the references be included as attachments to the calculation.

lc. 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 N Y Desig erfication of CakuadtionsN SY NMPAST-O.-O-01 and NMPAST-02.-00! " C(RN1o,4grfIOv NISYS4169-DVOO1IRO Document: NMPAST-01-001. RevI. 1

Review Check Items Addressed with Basis of Review Answer:-*h 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, the value-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 ýof the.

Unit 1 Reactor building is 422 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 mi2 . 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 NMPAST-01-001 , the reason for hand-checking 28 sector 0.5% X/Q values is not clear. (Recommend that an example be provided to clarify the screening process.) Of these 28 cases, 26 resulted in 0.5% XI/Q 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 inter.vals using 3 significant digits (hand-check 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 2,08.E-6 for Unit. 1 Main Stack to. LPZE,. 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 NUREG/GR-2858.states, "Starting with, thehighest 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/O values." The FORTRAN listing was .checked to verify that ENVLOP uses only ten points in each increment, thereby calculating the slopes of nine 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 logarithmic interpolation, it is recommended that the basis for using the selected time. points of 8, 16, 72 and 624 hours0.00722 days 0.173 hours 0.00103 weeks 2.37432e-4 months (as shown in the Intermediate Time Calculations spreadsheets), be stated.

Page 8 of!12

Nine MilePoWi, Nuclear Station Design,Verification of Calculations NIS YS CJNoR4TOiAJUN INMPAST-OI.O01 and NMPAST-02-O01 NISYS.1 169-DV0O0/RO Document: NMPAST-01-001. Rev. 1 Review ,Check Items Addressed.with Basis 0f* Review Answer Yes No N/A

4. Were the inputs correctly incorporated into the calculations? 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 arei provided on a read-only CD (Ref. 10), it is recommended that a detailed listing ýOf 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) 1.145?

Page 9 of 12

Nine Mile, Point Nuclear Station Design Verification of Calculations I-OF"N I S I S NMPAST-OI-O01 and NMPAST-02-001 NISYS-1169-DV001RO Design Verification Checklist Document: NMPAST-02-001, Rev. 1 ,Calculation of Atmospheric Design Verifier's Name:

DisDersion Coefficients fXQs) at the NMP Unit 1 Duane T. Nakahata Technical Support. Center and Units I and 2 ContrOl Room Intakes for All Releases Review Check Items Addressed with Basis of Review Answer Yes No N/A

1. Were the inputs correctly selected? X 1a. Although the values used for design inputs are referenced (in Sections 5.2 and. 7.1 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 Unit1 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.attachments to the calculation.

lb. 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. 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 Guidep23 be included.

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. U1 CR intake building wake area is assumed to be one-half of:the E-W U1 TB cross-sectional area because

[give reason] and this conservatively results in higher X/Q values."

As, another example, "U2 Main Stack release is: assumed to be a ground-level release in ARCON96. because [give reason], as described in Section 7.3."

3. Was an appropriate method used? X.

Page 10 of 12

Nine Mike PointNuclear Station NIS YS Design Verification.of Calculations NMPAST-OI-O01 andNMVPAST-02-O01 NISYS-1169-DVOO1/IO Document: NMPAST-02-001, Rev. 1 Review Check Items:Addressed with:Basis of Review Answer Yes, No lWA t *i I

4. Were the inputs correctly Incorporated into.the calculations? x 4a. In NMPASTW02-001, 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 25.06 m). 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 mi). These errors are carried, forward into Section 7.2, resulting in six errors in. the Table 7.21

.Building Wake Areas:

Unit 1 (all) to Unit 1 CR should be 550 not 167 m2 .

U 2 (a~llexceptstaCk) 'to Ul CR should be 623 not 281 in2 .

U2 stack to Ul CR shouldbe 21 65 not 1363.m 2.

U2 stack. to U1 TSC should be 3639 not 3549 m2.

U2 stack & SGB to U2.CR (all) should be 1844 not 1773 m2 .

U2 PASSIto U2 CR (all) should be 922 not 886 m.

The errors were carriedforward 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 a, read-only CD (Ref. 11), it is recommended that a detailed listing ofthe files be provided. This Will assure that thefiles available on hand and those discussed in the calculation are identical.

6ý the calculation conform to USNRC Regulatory Guide Does 1,194?

(RIG) X Page 11 of 12

Nine Mile~ Point Nuclear Staion Design Verification of Calculotions NISYS NMPAST-OIO01 and NMPAST-02-O01 / 0"oO'RA TION NISYS-1169-DVO01IR0 5.0 RECOMMENDATIONS

1. Correct or addresstihe 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 ýcalculations) of Section 4.

3. Evaluate the recommendations discussed in Items 1b, 1c, 3a, 3c, and 5 (for NMPAST-O1 -

001), and Items Ia, 11b, and 5 (for NMPAST-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, ifdesired.

5. Revise NMPAST-0i-001 and NMPAST-02-001, incorporating changes due to the recommendations stated above.

Page 12 of 12

DESIGN "V 7 NIS YS Attachment 1 VERIFICATIONORATIO CRITERIA I NISS169-DV 1R I II. Originator followed defined procedures.

Z 2. Title, purpose, and function of the work checked are adequately described.

Z 3. Work method is clearly stated and appropriate'.

z 4. Assumptions are identified. Open items are flagged for subsequent verification where necessary. See Item 2 of Section 4.0

[ 5. Technical bases andreferencesare current'and are correctly selected and incorporated.

-' 6. Design inputs are properly selected and adequately identified. Any. specific inputs to be excluded are adequately identified. See Item I of Section 4.0

7. Applicable codes, standards, and regulatory requirements are identified and properly used.

8.. Analytical steps can be verifiedwithout recourse to originator.

9' Each page of the work is identified and traceable to originator, date, and project or equivalent control number.

Z 10. All markings are legible and identifiable.

-1 11. Work clearly references any final supporting computer runs. Calc. needs index of computerfiles Z 12. Final computer runs or documents being checked include input listing. Correct inputs areused.

Where input is not listed on output, alternate methods are used by the checker.

[] !3. Final computer runs are Uniquely identified.

Z 144Results are consistent with inputs, technical procedures, and other projectcriteria.

Z 15. Results arereasonable.

Z 16.Revisions are clearly documented.

Z 17. Technical interface requirements in the Project Plan have been satisfied.

118. Appr.opriate QA requirements are specified.

L- 19. Applicable construction and operating experience has.been considered. N/A I 20. Specified parts, equipment, and processes are suitable for required application. NIA

[- 21. Specifiedmnaterials are compatible ýwith each .other and the design environmental conditions .to.

which the: material will be exposed. N/A E] 22. Adequate maintenance features andrequirements are specified. N/A El 23. Accessibility and other design provisions are adequatefor performance of needed maintenance and repair. N/A L 24. Adequate- accessibility is provided to perform the in-service inspection expected to be required during plant life. N/A

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 design requirements have been satisfactorily accomplished'. N/A FI' 27. Adequate handling, storage, cleaning, and shipping requirements are specified. N/A MI 28. Adequatelidentification. requirements are specified. N/A Design Verified: Calculation NMPAST-01-001 Revision: I Vciificr: 4~ik t7: Date: W NISYS QA Form 3.2 (JUL-2002) Page I of I

DESIGN NI SAttachment.2 VERIFICATION / CORPORATION NISYS 1169-DVOO1/RO CRITERIA 0 1. Originator followed defined procedures.

S2; Title, purpose, and function Of the work checked are adequately described.

15] 3. Work methodis clearly stated and appropriate.

[ 4. Assumptions, are identified. Open items are flagged "for subsequent verification where necessary., See item 2 of Section 4.0 Z 5. Technical bases andreferences are current and are correctly selected and incorporated.

D 6. Design inputs are properly selected and adequately identified. Any specific inputs to be excluded are adcquately identified. See Item 4 of Section 4.0 5 7. Applicable codes, standards, and regulatory requirements are identified and properly used.

S8, Analytical steps can be verified withoutvrecourse to originator.

S9. Each page of the work is identified and traceable to originator, date, and project or equivalent controlnumber.

] 10. All markings are legible and identifiable.

E] 11- Work clearly references any final Supporting computer runs.: Caic. needs index of computerfiles.

I 12. Final computer runs or documents being checked include inputlisting. Correct inputsare used.

Where,input is not listed on output, alternate methods are used by the checker.

] 13. Final computer runs are uniquely identified.

Z 14. Results are consistent with inputs, technical procedures, and:other project criteria.

1 15 Results are: reasonable.

S16. Revisions are: clearly documented.

Z 17. Technical interface requirements in: the Project Plan have been satisfied.

18. -Appropriate QA requirements are specified.

E"] 19. Applicable conistruction and operating experience has been considerked. N/A 1" 20. Specified parts, equipment, and processes are suitable for required application. N/A' Ei 21. Specified materials are compatible with each other and the design environmental conditions to Which the material will be exposed. N/A F1 22. Adequate-maintenance features and :requirements are specified. N/A

23. Accessibility and other design: provisions are adequate for performance of needed maintenance and repair. N/A F1 24. Adequate accessibility is, provided to perform the in-service inspection expected to be required duringplant life. NIA

-I 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 design requirements have been satisfactorily accomplished. N/A L- 27. Adequatehandling, storage, cleaning, and shipping requirements are specified. N/A LI 28. Adequate identification requirements are specified. N/A Design Verified.: Calculation NMPAST-02-001 Revision: I Verifier: A,- 7 , Date: 2 . .. ...

NISYS QA Form 3.2 (JUL-2002) Page [.of I

CERTIFICATE OF YS IAttachment 3 CONFORMANCE YCORPORATOP NISYS-1169-DVOO1/RO COC Number: COC1169-001 Date: 8/25/2003 Client: Nine Mile Point Nuclear Station, LLC NISYS Pmject No.:, 1169 NISYS Project

Title:

Nine Mile Point Calculation Design Verification Contract No./Date:. 00750 /RI 11/07101 P.O. No.IDate:' 03-45612 / 07/01/03 Supplier: NISYS Corporation NISYS Corporation certifies that the materials and products listed below were furnished to CLIENT.in conformance with the requirements of Purchase Order 03-45612 Customer NISYS Item No. Item No. Quantity Item Service Description 001. NISYS-1169-DV- 1 Design Verification of Calculations NMPAST-01-001 and

_00I/RO NMPAST-02-001 Prepared by.: Duane T. Nakahata, PhD, PEL (First, MI, Last) ProjectEngineerf (/1--.-'LA*.

2- *'

Printed I Typed Name and Signature Date Title NISYS QA Manager Mark R.Winsor, PE (First, M!, Last)_ ___AK .

Printed / Typed Name . 4 Signature Date NISYS QA Form 2A (JUL-2002) Page 1.of I

ML070110321

Text

2. Background

Subject:

Attachment:

Subject:

Subject:

Attachment:

3.0 REFERENCES

3.0 REFERENCES

Title:

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