Text

.Calculation 32-5052821-01, Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 & 1.194 Methodologies
	ML043650064
Person / Time
Site:	Pilgrim
Issue date:	12/06/2004
From:	Hamawi J; AREVA
To:	; Office of Nuclear Reactor Regulation
References
	32-5052036-00, 32-5052125-00, 32-5052821-01
	Download: ML043650064 (158)
	v • d • e

Attachment 3 to 2.04.115 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Soecifications Areva Document No. 32-5052821-01, "Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies" (80 pages);

Areva Document No. 32-5052036-00, "Evaluation of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data' (32 pages); and Areva Document No. 32-5052125-00, "Conversion of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96" (16 pages)

20032-33 (6/23/2004 RELEASE DATE JA DOCUMENT RELEASE NOTICE AR EVA RM INITIALS CONTRACT NUMBER PLANT CC OR CHARGE NUMBER

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Determination of Atmospheric Dispersion N/A 32-5052821-01 Factors for Accident Analyses Using Reg S

N Y

N Guilde 1.145 and 1;194 Methodologies KEYWORDS (For Informtlonal Purposes Only)

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ACALCULATION

SUMMARY

SHEET (CSS)

AR EVA Document Identifier 32-5052821-01 Title Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies PREPARED BY:

REVIEWED BY:

METHOD: 3 DETAILED CHECK 0 INDEPENDENT CALCULATION NAME Theodore A. Messier NAME John N. Hamawi SIGNATURE dft/asAuK SIGNATURE TITLE Meteorologist DATE D-03rOLf TITLE / Zonsulting Radiological Eng.

DATE COST REF.

TM STATEMENT:

CENTER 41758 PAGE(S) 14-1S REVIEWER INDEPENDENCE pi PURPOSE AND

SUMMARY

OF RESULTS:

Purpose Determine'atmosphericdispersion factors for accident analyses using Regulatory Guide 1.145 and 1.194 methodologies as requested in EntergylPilgrim Contract Order Number 4500534887 (Reference 1).

Results Atmospherc dispersion factors (xlas) determined using Regulatory Guide 1.145 and 1.194 methodologies and suitable for use in accident analyses are presented in Section 7.0.

Purpose and Reason for Revision This calculation was revised to: correct a typographical error on page 6, to provide an explanation of why five years of meteorological data were used in the analysis, to provide a new compact disk to the client This calculation is safety related and was prepared under the AREVANFramatome ANP Quality Assurance Program.

THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFETY-RELATED WORK CODE/VERSIONIREV CODENERSIONIREV aeolus3 1.0 ARCON96 1.0 YES 7

NO Framatorne ANP, Inc., an AREVA andSlemens company Page jI of 80

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an ARE VA and Siemens company Document ID 32-5052821-01 Page 2 RECORD OF REVISIONS (Note that in addition to this record of revisions page. revision bars have been included on affected Daaes.)

Revision Number Section Description 1

All Changed revision number portion of the calculation number from 00 to 01.

1 Record Of Revisions, page 2 Added changes to the Record of Revisions page.

1 3.0, page 6 Fixed typographical error in section three - change met data dates from 1999-2001 to 1996

- 2000. Added footnote with explanation of why five years of meteorological data were used and why the 1996 - 2000 period was used.

Compact Disc Provided new compact disc with met data file times that match those in Attachment C.

22410-3 (5/10/2004) 1 of2 At DESIGN VERIFICATION CHECKLIST AR EVA Document Identifier 32-5052821-01 Page 3 of 80 Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 Title and 1.194 Methodologies

1.

Were the inputs correctly selected and incorporated into design or analysis?

N E

N/A

2.

Are assumptions necessary to perform the design or analysis activity adequately El N E

N/A described and reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?

3.

Are the appropriate quality and quality assurance requirements specified? Or, for E

a N

al N/A documents prepared per FANP procedures, have the procedural requirements been met?

4.

If the design or analysis cites or is required to cite requirements or criteria based upon E

Y D N ENIA applicable.codes, standards, specific regulatory requirements, including issue and addenda, are these properly identified, and are the requirements/criteria for design or analysis met?

5.

Have applicable construction and operating experience been considered?

a Y

El N E

N/A

6.

Have the design interface requirements been satisfied?

El Y E

N

[

N/A

7.

Was an appropriate design or analytical method used?

EVY El N E

N/A

8.

Is the output reasonable compared to inputs?

Y ElN El N/A

9.

Are the specified parts, equipment and processes suitable for the required application?

a Y

E N

N/A

10.

Are the specified materials compatible with each other and the design environmental Y

El N IWN/A conditions to which the material will be exposed?

11.

Have adequate maintenance features and requirements been specified?

° Y

El N E' N/A

12.

Are accessibility and other design provisions adequate for performance of needed El Y E

N Et N/A maintenance and repair?

13.

Has adequate accessibility been provided to perform the in-service inspection expected El Y El N ER/N/A to be required during the plant life?

14.

Has the design properly considered radiation exposure to the public and plant

° Y

El N

[

N/A personnel?

15.

Are the acceptance criteria incorporated in the design documents sufficient to allow

[

Y El N a

N verification that design requirements have been satisfactorily accomplished?

16.

Have adequate pre-operational and subsequent periodic test requirements been E

Y E

N N/A appropriately specified?

17.

Are adequate handling, storage, cleaning and shipping requirements specified?

E Y

El N

__/N_

A

18.

Are adequate identification requirements specified?

E Y 0

N Ef N/A

19.

Is the document prepared and being released under the FANP Quality Assurance UrY El N E° NIA Program? If not, are requirements for record preparation review, approval, retention, etc., adequately specified?

Framatome ANP, Inc., an AREVA and Siemens company

2420 -3 (5110/2004) 2 of2 A

DESIGN VERIFICATION CHECKLIST AR EVA Document Identifier:

32-5052821-01 Page 4 of 80 Comments:

Verified By:

John N. Hamawi (First, Ml, Last)

Printed / Typed Name Signature Date Framatorne ANP, Inc., an AREVA andSiemens company

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 AAccident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by: Theodore A. Messier Page 5 Framatome ANP, Inc, an AREVA and Siemens company TABLE OF CONTENTS CALCULATION

SUMMARY

SHEET (CSS).............................

I RECORD OF REVISIONS..............................

2 DESIGN VERIFICATION CHECKLIST.......................................................................................3 TABLE OF CONTENTS..............................

S 1.0 Purpose/Objective

.6 2.0 Assumptions and Key Assumptions......................

6 3.0 Design Input

.6 4.0 Computing Environment.1 5.0 Quality Assurance.10 6.0 Calculations........................................................................................................................... I0 7.0 ResultslConclusion

.I 8.0 References.14 ATTACHMENT A INPUT REQUIREMENTS FOR AEOLUS3....................

......................... 21 ATTACHMENT B: AEOLUS3 INPUTS FOR MS AND GROUND RELEASES........................................ 35 ATTACHMENT C: COMPUTER INPUT AND OUTPUT FILE NAMES..........................................

41 ATTACHMENT D: ARCON96 SOFTWARE INSTALLATION TEST RECORD........................................ 44 ATTACHMENT E: ARCON96 OUTPUT.............................................

45

A Deternminaton of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by: Theodore A. Messier Page 6 Framnatome ANP, Inc., an AREVA and Siemens company 1.0 PurposelObjective Determine atmospheric dispersion factors (X/Q's) for accident analyses using Regulatory Guide 1.145 and 1.194 methodologies as requested in EntergylPilgrim Contract Order Number 4500534887 (Reference 1).

2.0 Assumptions and Key Assumptions

The maximum allowable plume centerline height is assumed to be the same as the annual average mixing layer height.

Gamma XIQ's were determined using a relative concentration of 1.0 for a single radionuclide, Xe-133. This is a conservative assumption supported by aeolus3 test runs documented in this calculation.

Distance from the Main Stack and the Turbine Building to the Low Population Zone (LPZ) is assumed to be the same as the distance from the Reactor Building to the LPZ. This is reasonable considering the distance in question (6840 meters).

Releases from the Reactor Building vent are at a height that is less than 2.5 times the height of adjacent solid structures and are therefore assumed to be ground level releases.

The Yard release point-is assumed to be a ground level release.

No building wake credit is taken for the Yard release point although plume meander credit is accounted for.

Releases from the Turbine Building roof are at a height that is less than 2.5 times the height of adjacent solid structures and are therefore assumed to be ground level releases.

Releases from the Turbine Building roof exhausters are assumed to occur from the roof exhauster that is closest to the receptor locations.

Releases from the Turbine Building Reactor Feed Pump area roof exhausters are assumed to be funneled to one release location.

Releases from the Reactor Building Truck Lock are at a height that is less than 2.5 times the height of adjacent solid structures and are therefore assumed to be ground level releases.

For ground level releases modeled using the computer code aeolus3, terrain heights are not used. (Per Reg.

Guide 1.145, release-point and receptor elevations are assumed to be the same.)

A key assumption is any assumption or limitation that must be verified prior to using the results and/or conclusions of a calculation for a safety-related task. There are no key assumptions in the present calculation.

3.0 Design Input

The meteorological data used in these analyses were obtained from References 5 and 6; they cover a five-year period from 1996 to 2000.1

The wind speed classes used in the aeolus3 computer runs were obtained from Reference 7.

Distances from the Main Stack, Reactor Building, and Turbine building to the Exclusion Area Boundary (EAB) were determined using References 8, 9, and 10.

Terrain heights between the Main Stack and the EAB, with respect to the grade at the base of the Main Stack, were determined using Reference 8.

Plume rise was not allowed even though the SGTS would be on.

Five years of hourly meteorological data were used because Reg. Guide 1.194 states that a five year period is considered to be reprensentative of long-term trends at most sites. The five year period from 1996 to 2000 was used in order to compare results with a previous calculation performed by PNPS (PNPS-I-ERHS-1I.B-3).

A AREVA Determinafon of Atmospheric Dispersion Factors for AccidentAnalyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Frarnatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 7 All other design inputs were received from the Pilgrm Nuclear Power Stafion (Reference 2); the data are presented in Exhibit 1.

The -8 time interval forthe LPZ y/Q's in Reg. Guide 1.145 was conservatvely subdivided into two intervals, namely 0-2 and 2-8. The 0-2 interval is more suitable for short term releases than the 0-8 interval.

lWind speed group upper limits I (Reference 7) l0.45, 1.0, 2.0, 3.0, 4.0, 5.0, 6.0, 8.0, 10.0. 13.0, 18.0. >18.0mlsec (use 22.4) 1 Distances from Release Points to Exclusion Area Boundary2 (References 8, 9,10)

Reactor Turbine SECTOR Main Stack Building Building (based on True North)

Dist.(m)

Dist. (m)*

N 373.2 492 534 NNE 492 486 528 NE 492 486 528 ENE 516 510 558 E

660 585.6 571.2 ESE 801.6 565.2 554.4 SE 540 471.6 415.2 SSE 393.6 350.4 302.4 S

295.2 331.2 279.6 SSW 270 301.2 255.6 SW 270 301.2 255.6 WSW 270 301.2 255.6 W

285.6 320.4 277.2 WNW 310.8 411.6 344.4 NW 310.8 507.6 498 NNW 313.2 511.2 498

Distances determined from the nearest point on the building to the EAB within a 45-degree sector centered on the compass direction of interest (Reg. Guide 1.145).

2The exclusion zone overwateris 500 yards (1500 feet) from the Intake structure head wall. The area would be a roughly rectagular shape runnig from property line to property ine, and along the N 11690 grid line of the plant coordinate system (see drawng C2).

A AREVA Determinaton of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Frarnatomc ANP, Inc., an AREVA and Siemens company Document ID 32-5052821-01 Page 8 I

SECTOR Main Stack Terrain Height (m above MS grade)

(Reference 8, at EAB distances)*

N 1.5 NNE 1.5 NE 1.5 ENE 1.5 E

1.5 ESE 1.5 SE 1.5 SSE 1.5 S

1.5 SSW 4.6 SW 4.6 WSW 4. 6 W

4. 6

.WNW 0.0

'NW__

'0.0-.

NNW 0.0 Terrain heights are the maximum values from the release point grade to receptor.

DESCRIPTION VALUE Sensor heights of primary meteorological tower above stack grade 220', 33' Delta-temperature sensor separation 220'-33' = 187' ws - mph; wd - degrees from True North; Units for all met parameters temperature - degrees Fahrenheit; delta-temperature - degrees Fahrenheit per 187' Main Stack Release Point: grade at stack base 65' Main Stack Release Point: height above stack base grade 335' Main Stack Release Point: height of adjacent solid structures

=15' Main Stack Accident Flow rate (used in ARCON96 for downwash effect) 4000 scfm Main Stack diameter 28.75 inches or 0.73 meters Effective height, MS release point to Control Room intake 335 65) = 327' Effective height, MS release point to Technical Support Center intake 335' (intake is below stack grade)

Turbine Building grade elevation 23' Turbine Building Release Point elevation 108' Turbine Building Release Point: release height above grade 85' Turbine Building Release Point: cross-sectional area for building wake 2116m2 Turbine Building Reactor Feed Pump Release Point: grade 23' Turbine Building Reactor Feed Pump Release Point (RFP): elevation 82' Turbine Building Reactor Feed Pump Release Point release height 59' Turbine Building Reactor Feed Pump Release Point: cross-sectional 406m2 area for building wake Reactor Building Vent Release Point grade 23' Reactor Building Vent Release Point elevation 182'

A AREVA Determinaton of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP_ Inc.. an AREYA and Siemens company Document ID 32-5052821-01 Page 9 I

DESCRIPTION VALUE Reactor Building Vent Release Point release height above grade 159' Reactor Building elevation for building wake effects 166' (Reference 11)

Reactor Building Vent Release Point: cross-sectional area for building 1886m2 wake Reactor Building Truck Lock Release Point: grade 23' Reactor Building Truck Lock Release Point elevation 43' Reactor Building Truck Lock Release Point: release height 20' Reactor Building Truck Lock Release Point: cross-sectional area for 1382m 2 building wake Control Room Receptor, grade elevation 23' Control Room Receptor elevation of air intake 73' Control Room Receptor. distance and direction to Main Stack 800', 303° Control Room Receptor. distance and direction to Turbine Building roof 138', 2070 exhausters Control Room Receptor distance and direction to Turbine Building 186', 2730 Reactor Feed Pump Area Control Room Receptor distance and direction to Reactor Building vent 160', 2850 Control Room Receptor. distance and direction to Reactor Building truck 248', 3150 Lock Control Room Receptor distance and direction to Reactor Building North 150' (rounded down to 45m in the ARCON96 Wall run), 3450 Technical Support Center Receptor grade elevation 23' Technical Support Center Receptor, height of air intake above grade 10' Technical Support Center Receptor: distance and direction from intake to 920' 3040 Main Stack 920_,_304_

Technical Support Center Receptor distance and direction to Turbine 190' 256° Building roof exhausters Technical Support Center Receptor distance and direction to Turbine 300', 2850 Building RFP Technical Support Center Receptor. distance and direction to Reactor 280', 2900 Building vent Technical Support Center Receptor. distance and direction to Reactor 390', 3100 Building truck Lock Technical Support Center Receptor. distance and direction to Reactor 240', 3250 Building North Wall

.n_

Reactor Building North Wall Release Point grade 23' Reactor Building North Wall Release Point: release heights above grade 2.0 m Reactor Building North Wall Release Point cross-sectional area for 1860m2 building wake Annual average mixing height 630m Exclusion area boundary distances and terrain heights See Drawings, use actual property line north Exclusionareaboundarydistancesandterrainheightsof Rocky Hill Road

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREV' andSiemens company Document ID 32-5052821-01 Page 10 I

DESCRIPTION VALUE Yard Area Release Point: release height, receptor height, 0

Yard Area Release Point receptor height 0

Yard Area Release Point site boundary/EAB distances from Yard Area Use circular 0ngs at 10, 50, 100, 200, 300, Wind speed to be assgned to calms 0.225 mrnsec (0.5 mph)

Distance to LPZ (assumed the same for all release points) 6840m N

0.0 NNE 0. 0 NE 0.0 ENE 0. 0 E

0.0 ESE 4. 6 SE 7.6 Main Stack Release Point: LPZ terrain heights above MS grade SSE 53.3 (feet)

S

93. 0.

SSW 102.1 SW 59.4 WSW 59.4 W

41.1 WNW 32.0 NW 7.6 NNW 0.

4.0 Computing Environment The computer runs in this calculation involved the use of computer codes aeolus3 and ARCON96 and were carried out on the HP 90001785 CPU running the HP UX B.10.20 operating system and a Dell Optiplex GX240 (serial number DVKPM1 1) running the Microsoft Windows XP operating system, respectively. Computer codes aeolus3 and ARCON96 are listed in the Framatome-ANP Computer Software Index. They are safety-related computer codes used to produce atmospheric dispersion factors using the methodologies of Regulatory Guides 1.145 and 1.194, respectively. There are no open software error reports for aeolus3 or ARCON96. The software installation test record for ARCON96 for the present calculation is provided in Attachment D.

5.0 Quality Assurance This work was performed under Framatome's Quality Assurance Program, and Framatome Procedure 0402-01 (Preparing and Processing FANP Calculations) was followed.

6.0 Calculations Meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2000 and evaluated in Reference 5 were used in determing the X/Q's. These data were reformatted for use with computer code ARCON96 in Reference 6.

Input requirements for the aeolus3 computer code are provided in Attachment A. Inputs for all aeolus3 runs are provided in Attachment B. Inputloutput for all ARCON96 runs are provided in Attachment E.

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodotogies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821 -1 Page 11 I

The input and output files have been stored on the FANP COLD server for archival storage and written to a compact disc for PNPS. A listing of the file names is provided in Attachment C.

Other cases were included for informational purposes and potential future use.

7.0 ResultslConclusion The following tables present atmospheric dispersion factors (X/Q's) determined using Regulatory Guide 1.145 and 1.194 methodologies, as implemented in computer codes aeolus3 and ARCON96 respectively, which are suitable for use in accident analyses. The appropriate Main Stack to Control Room and Main Stack to Technical Support Center X/Q's for use in radiological habitability analyses are presented in Tables 7.8 and 7.9.

Note that the X/Q's for MS to the CR and TSC (in Tables 7.1 and 7.2) are for direct transfer from the stack to the respective air intakes. They do not include the contributions of recirculation effects as specified in Reg. Guide 1.194.

The applicable logic from this guide is as follows:

The maximum non-fumigatUon X /Q value obtained for the 0-2 hour interval using aeolus3, which implements the Reg Guide 1.145 methodology, was compared to the corresponding value obtained using the ARCON96 methodology, and the higher value was selected for use in habitability assessments,

The X /Q values obtained using the ARCON96 methodology for the 2-8 hour and 8-24 hour intervals are the values to be used in habitability assessments, For the remaining time intervals (namely, 24-96 and 96-720 hours), a weighted average of the X /Q values obtained using both methodologies are the values to be used in habitability assessments.

The equation used to perform the weighted average for each interval is:

zIQ=[1* (X/ Q)

W1.145 + 23* (X Q) AXN ]/24 The appropriate MS to CR and TSC XIQ's for use in radiological habitability analyses are presented in Tables 7.8 and 7.9 under the heading RG 1.194.

Table 7.1: Control Room Atmospheric Dispersion Factors (Concentration X/Q) From ARCON96 To Control Room From.

Main Stack*

Turbine TB Reactor Reactor Reactor Reactor Building Feed Pump Building Vent Building Truck Building North Area Lock Wall Time Interval (s/m 3()

(srl 3)(s/r

3)

(s/r3)(s/r 3) 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4.01 E-07 3.56E-03 1.99E-03 1.76E-03 9.72E-04 2.36E-03 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.02E-07 3.11 E-03 1.69E-03 1.25E-03 7.52E-04 1.60E-03 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6.1 8E-08 1.26E-03 6.67E-04 4.26E-04 2.80E-04 6.10E-04 1 -4 days 5.89E-08 1.10E-03 5.17E-04 3.67E-04 1.93E-04 4.37E-04 4 -30 days 5.05E-08 9.52E-04 4.67E-04 3.15E-04 1.61 E-04 3.51 E-04

These XIQ's are not to be used as-is for radiological habitability analyses per Reg. Guide 1.194; see Table 7.8.

A ARE VA Determinafon of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatorne ANP, Inc., an ARE VA and Siemens company Document ID 32-5052821-01 Page 12 I

I Table 7.2: Technical Support Center Atmospheric Dispersion Factors (Concentration X/Q) From ARCON96 To Technical Su port Center From +

Main Stack*

Turbine TB Reactor Reactor Reactor Reactor Building Feed Pump Building Vent Building Truck Building North Area Lock Waft Time Interval (sr 3)

(sIM3) s/r3 (sIM3)

(s/M3)

(s/mr3) 0-2 hours 5.14E-07 1.72E-03 7.73E-04 6.94E-04 4.27E-04 1.04E-03 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.85E-07 1.54E-03 6.40E-04 4.91E-04 3.45E-04 7.44E-04 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.04E-08 5.67E-04 2.55E-04 1.67E-04 1.27E-04 2.83E-04 1 -4 days 7.48E-08 4.96E-04 1.86E-04 1.41 E-04 9.13E-05 1.85E-04 4 - 30 days 6.46E-08 4.1 0E-04 1.69E-04 1.22E-04 7.39E-05 1.63E-04

These XlQ's are not to be used as-is for radiological habitability analyses per Reg. Guide 1.194; see Table 7.9.

Table 7.3: EAB/LPZ Atmospherc Dispersion Factors for Main Stack Releases From aeolus3 Receptor Time Concentration Critical Distance Gamma' Sector Distance Interval XIQ (s/M

3)

Sector (m) from XIQ (s/m

3)

(m) from (hours)

MS MS EAB Fumigation 1.820E-04 SSW 270.0 9.960E-05 SSW 270.0

_ 0-2 2.812E-06 SSE 393.6 7.390E-06 WNW 310.8 LPZ Fumigation 1.908E-05 S

6840.0 1.503E-05 SSE 6840.0 0 -2 4.541 E-06 SSW 6840.0 6.248E-06 WNW 6840.0 2-8 2.258E-06 SSW 6840.0 2.943E-06 WNW 6840.0 8-24 1.210E-06 SSW 6840.0 1.502E-06 WNW 6840.0 24 -96 4.651 E-07 SSW 6840.0 5.534E-07 6840.0 96 -720 1.178E-07 SSW 6840.0 1.361E-07 6840.0

Direction-independent (all sectors combined)

- Comparison of the aeolus3 outputs from cases mstoeab and mstoeab2, and cases mstolpz and mstolpz2 shows that Xel33 leads to higher gamma XIQ's than 0.2MeV, with the exception of the EAB 0-2 hour value. The listed value in the table is for Xe133; the value for 0.2 MeV is 8.632E-06.

Table 7.4: EABILPZ Atmospheric Dispersion Factors for Turbine Buildinq Releases From aeolus3 Receptor Time Concentration Critical Distance Gamma Sector Distance Interval XIQ (sIM3)

Sector (m) from TB XIQ (s/m3)

(m) from TB (hours)

EAB 0-2 8.631E-04 WSW 255.6 3.234E-04 NE 528.0 LPZ 0-2 3.692E-05 NE 6840.0 3.706E-05 NE 6840.0 2 -8 1.929E-05 NE 6840.0 1.856E-05 NE 6840.0 8 - 24 1.080E-05 NE 6840.0 1.001 E-05 NE 6840.0 24-96 4.441E-06 NE 6840.0 3.885E-06 NE 6840.0 96 -720 1.239E-06 NE 6840.0 9.978E-07 NE 6840.0

A ADREVA Determinabon of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP, Inc., anAREVA and Siemenscompany Document ID 32-5052821-01 Page 13 I

I Table 7.5: EABILPZ Atmospheric Dispersion Factors for Reactor Building Releases From aeolus3 Receptor Time Concentration Critical Distance Gamma Sector Distance Interval XIQ (s/M

3)

Sector (m) from TB XIQ (s/m

3)

(m) from TB (hours)__

EAB 0-2 7.479E-04 NE 486.0 3.199E-04 NE 486.0 LPZ 0-2 3.692E-05 NE 6840.0 3.551 E-05 NE 6840.0 2 - 8 1.915E-05 NE 6840.0 1.782E-05 NE 6840.0 8-24 1.066E-05 NE 6840.0 9.627E-06 NE 6840.0 24 -96 4.339E-06 NE 6840.0 3.745E-06 NE 6840.0 96 -720 1.194E-06 NE 6840.0 9.656E-07 NE 6840.0 Table 7.6: Maximum Offsite Atmospheric Dispersion Factors for Main Stack Releases From aeolus3 (CR Case)

Receptor Distance (m)

Time Interval (hours)

Concentration XIQ (s/r3) 400 0-2 3.926E-06 400 2-8 2.203E-06 400 8-24 1.316E-06 400 24-96 5.966E-07 400 96-720 1.926E-07 I

Table 7.7: Maximum Offsite Atmospheric Dispersion Factors for Main Stack Releases From aeolus3 (TSC Case)

Receptor Distance (m)

Time Interval (hours)

Concentration X/Q (s/m3) 400 0-2 3.681 E-06 400 2-8 2.069E-06 400 8 -24 1.237E-06 400 24-96 5.622E-07 400 96 -720 1.828E-07 Table 7.8: Control Room Atmospheric Dispersion Factors (Concentration XIQ ) for Main Stack Releases (Rea. Guide 1.194)

ARCON96 aeolus3 RG 1.194 Time Interval XIQ X/Q XIQ (sec/m3)

(sec/m3)

(seclm3)

From Table From Table 7.1 7.6 0-2 hours 4.01E-07 3.93E-06 3.93E-06 2-8 hours 3.02E-07 2.20E-06*

3.02E-07 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6.18E-08 1.32E-06*

6.18E*08 24-96 hours 5.89E-08 5.97E-07 8.13E-08 96-720 hours 5.05E-08 1.93E-07 5.64E.08

Not applicable

A

.AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Franatomc ANP. Inc, an AREVA and Siemens company Document ID 32-5052821-01 Page 14 I

Table 7.9: Technical Support Center Atmospheric Dispersion Factors (Concentration X/Q) for Main Stack Releases (Reg. Guide 1.194)

ARCON96 aeolus3 RG 1.194 Time Interval XIQ XIQ XIQ (seclm3)

(seclm3)

From Table From Table 7.2 7.7 0-2 hours 5.14E-07 3.68E-06 3.68E-06 2-8 hours 3.85E-07 2.07E-06*

3.85E-07 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.04E-08 1.24E-06*

8.04E-08 24-96 hours 7.48E-08 5.62E-07 9.51 E-08 96-720 hours 6.46E-08 1.83E-07 6.95E.08

Not applicable I

Table 7-lft Worst,FrnrAtmn-.nherirn fi-,nerinn Far~tor-(Cnncrentratinn 'vOlfor Yard Are-a Relp.a;-es From aenltiiq Receptor 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months Distance (m)

(seclm3)

(seclm3) 10 7.713E-01 4.883E-01 3.247E-01 1.737E-01 7.072E-02 50 4.208E-02 2.653E-02 1.757E-02 9.342E-03 3.771 E-03 100 1.232E-02 7.725E-03 5.093E-03 2.689E-03 1.075E-03 200 3.493E-03 2.189E-03 1.443E-03 7.610E-04 3.038E-04 300 1.757E-03 1.096E-03 7.190E-04 3.767E-04 1.490E-04 400 1.088E-03 6.757E-04 4.417E-04 2.302E-04 9.029E-05 500 7.485E-04 4.633E-04 3.019E-04 1.566E-04 6.098E-05 Table 7.11: Worst Sector Atmosph ric Dispersion Factors (Gamma X/Q ) forYard Area Releases From aeolus3 Receptor 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months Distance (m)

(seclm3)

(sec/m3)

(seclm3) 10 5.653E-03 3.504E-03 2.298E-03 1.217E-03 4.897E-04 50 2.603E-03 1.630E-03 1.073E-03 5.656E-04 2.254E-04 100 1.629E-03 9.923E-04 6.374E-04 3.233E-04 1.220E-04 200 9.388E-04 5.547E-04 3.468E-04 1.68BE-04 6.OOOE-05 300 6.960E-04 4.017E-04 2.459E-04 1.158E-04 3.932E-05 400 5.629E-04 3.191E-04 1.923E-04 8.841E-05 2.898E-05 500 4.610E-04 2.588E-04 1.546E-04 7.014E.05 2.255E-05 I

8.0 References 1.

2.

3.

EntergyJPilgrim Contract Order Number 4500534887.

Entergy Nuclear Generation Company, Pilgrim Nuclear Power Station letter NESG 04-098, October 27, 2004.

U.S. Nuclear Regulatory Commission Regulatory Guide 1.145, 'Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants', Revision 1, November 1982.

A Determinaton of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies AREVA Prepared by. Theodore A. Messier Page 15 Framatome ANP. Inc., an AREVA and Siemens company

4. U.S. Nuclear Regulatory Commission Regulatory Guide 1.194, 'Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plantse, June 2003.

5. AREVAIFANP Calculation 32-5052036-00, "Evaluation of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data", dated November 2004.

6. AREVANFANP Calculation 32-5052125-00, 'Conversion of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON 96t dated November 2004.

7. ANSI/ANS-2.5-1984, American National Standard for Determining Meteorological Information at Nuclear Power Sites, dated September 14, 1984.

8. PNPS Drawing C-2, Rev. E9, Site Plan, April 2000.

9. PNPS Drawing C-1, Rev. E2, Site Plan, 3-15-79.

10. PNPS Drawing A-105, Rev. 2, Access Control & Radiation Zones General Station Yard Areas Operation &

Shut Down, 8-24-73.

11. PNPS Drawing A-1 6, Rev. E3, Turbine and Rector Buildings North & South Elevations, 11/95.

A AR EVA Detemination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by-Theodore A. Messier Framnatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052821-01 Page 16 I

Exhibit 1: Design Input Data Transmitted by PNPS

- Entergy N

S October 27. 2004 NESG 04-098 Richard J. Cacciapouti Manager, Nuclear & Radiation Engineering Framatome ANP, Inc.

400 Donald Lynch Boulevard Marlborouph, MA 017752.,

Dear Mr. Cacciapouti:

The following Information is to be used by Frarnatome ANP in support of Pilgrim Station Fuel Handling Accident calculations. See Attachment 2 below.

My only concern with these design Inputs is that physical lengths are expressed in feet and meters. This Is due to the reference documents that support the values. Having a mixture of units is a potential error (rap. I caution you and your staff to be highly sensitized to this observation.

Should you have any questions, please call me directly at 508-830-7832.

Sincerely Yours.

)a. hi.A Dr rd Mogol I Senior Project Manager Attachment FJM:jmp

A AR EVA Determnation of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Frantatorne ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 17 I

PNPS MET DATA AND X1O

- DESIGN INPUT No.

DESCRIPTION I

VALUE REFERENCE A

Mel Data A1 Sensor hei~ts for 220 bot mreteorologial lower 2201t.

33ht 2. Page B-1 and B-168 A2 Derhaterrperature sensor saparation 22X -33tt

2. Page B-2 VIS - nptx WD -degrees torn True Noth temperature -

A3 Uritsforalmnetpararneers degree NA -Standardi Units Fahrenheit; delta.

lternperaturg -

detees Fahrenheia per 18711 B - ARCON96 bts" B1 Main Stack Release Point 92!e a stack base 65h1 1

M2 Uan Stack Release POirt height above stack base gade 335tt

2. App. 8, page B-15 B3 Main Stack Release Point height of e t

acserdolhd sttruchures 15t 1

84 Tuwbine E

cMd gradeelevation 23ft tO B5 Turbine Bu Rdin Release Point elevation 108t1 10 86 Turbine BuBL"ut Release Pofnt release height 8511 l0 Turbine 8dOtuin Release Pont crmss-sectionat area lor B7buildg wake 2ttm 5,t0 B8 Turbine u1*Vg Reaftr Feed PFnp Release Point: prade 231t 10 B9 Tbine Bulkig Reactor Feed Pump Rlease PointB:

t elevation B10 Turbine Buidng Reactor Feed Pump Release Point release 59ft 10 Turbine Bal dng Reactor Feed Puntp Release Point cross-I 1 ec0onal area tor buitdng wake 406nB 5.10 B12 ReactorBuldfgVen ReleasePoint grde 23n 9

813 ReaorBuildingVent ReleaaPohn eevation 18211 8

B14 Reactor Buidng Vent Release Point release height 159h 8g9 B15 Ractor Biding Vent Relse Point: cros-seion area 7

l or buiitdin wake I

18 816 Reactor Bulding Truckock Release Poirt grade 2

9 B17 Reador BuldsgTjck RlckR asa Pdont:el vation 4a 8

B18 Reaaorhudg Tnruok PR ase Poirt: release hei 2V 8.9

A AR EVA Deterrninaion of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Franataome ANP. Inc.. anAREVA andSiemens company Document ID 32-5052821-01 Page 18 I

A AREVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 19 I

C

AEOLUSS C1

_M m

6 12.1NO82-t4 Se D'air~gs.

U5J adtu8 uu ttiOf C2 propaort "

y ri i

Pns I15.

15 r_

d ofP4dq

.Kit ROM The =ktim zcn Of er cmwM 1 5W ySX ( 11500 Ife) hm the Inakb hucre hat wiat The cO aea woviM ber itoumy 1cwq2V Owo brm po k

l ropnere.

On W F

wirVN C2he ISW k wojd be abord I-71 ki of tN11500 Ine.

C4 Yedra~pm ease PwC,--.he0 1114ehae irof 0 i tfp~w lor Y0 RRepl t

F hw4 sg A

tit a3 syMpd br CUrd:hbe_

Yco t.fiiseP n bvAwAl~ncsfo Vrgsi10.50. AswTTFm CsYadArea 10r0

,200.300, rp 100 SW. 500.

C7 W4 lo be t ca 0225n1ftc 4

CS. DWW" I LPZ (essbufrm.0 one am for a" rahN 684l 3=

0.0 0.0 0.0 0.0 D:0 4.8 7.

53.3 M0C9 sP~ PW t.~rao S

920 2.Tabie B.3-1 59.4 5IA 41.1 32.0 7.5 0.0

67 _lac OWnVW 3,5 6rt dasctw 387 Incs m ~3r~ifecec 3

Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 A

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by: Theodore A. Messier Page 20 Framatome ANP, Inc, an AREI'A and Siemens company REFERENGES

1. PNPS Drawing M23, Equipment Location Main Slack & Filer Building.

2. Pilrlm Station Unit I Appendix I Evaluation, April 1977.

3. PNPS Fal Sa"etyAnalysis Rsport, Chapter 14, Table 14.5-2. Revision 15, June 1993.

4. Manual PNPS-1 -ERHS-XIX.Q-54, Revision 0, *RCP User's Manual For Program AEOWS-3.

S&SACP-29, Revision 0. Software Catalog hem #01379.

5. PNPS Drawing M14, Equipntml Locatin Turbbie Buldidg Plan El. 51't

6. PNPS Drawing MlB. Equipment Location Raor Building Plan El. 51'.T

7. PNPS Drawing M19, Equipment Location Reactor Building Plan El. 74'-3& El. 91-3 E. PNPS Drawing M22, Equipment LocaUm Reactor Buldng Section C-C

9. PNPS Drawing M23. Equipnit Location Sction D-O Y L-L

10. PNPS Drawing M24, Equiprent Location Sections E-E and F-F.

11. PNPS Drawing M26, Equipment Location Sections: Hf. J-J, & K-K.

12. PNPS Drawing C2, Rev. E9. Site Plan.

13. PNPS Drawing AO, Tuwbne and Reacto Building Root Plan.

14. PNPS Drawing M646, Technical Suppout Center Mechanical Floor Plan.

15. PNPS Drawing C1. Rev. E2, Ste Plan.

16. PNPS Drawing A-105, Rev.2, Access Control & Radiation Zones Genoral Station Yard Areas OpealIon & ShW Down.

17. PNPS Drawing M-289, Reactor Bulft Air Flow Diagrarm

16. PNPS Unit 1 Appmndix I Evaluation, April 1977.

A iDetermination of Atmospheric Dispersion Factors for A-\\

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by Theodore A Messier Framatomc ANP, Inc.. an AREVA and Siemens company ATTACHMENT A: INPUT REQUIREMENTS FOR AEOLUS3 AEOLUS3 MOD 01 Input Data Requirements Plant and Receptor Data Document ID 32-5052821-01 l

Page 21 Input Line 1 (20A4)

Col. 1-80 Input Line 2 (1615)

Col. 5 Col. 10 Col. 14-15 TITLE Any alphanumeric characters for problem identification.

Program control options KOPT Application option, as follows:

(a)

I =

Continuous, routine releases (b) 2 =

Intermittent releases (c) 3 =

Accidental releases KPRINT Printout control option, as follows:

(a) 0 Short printbot (which includes the input data and final summaries)

(b) 1 Full printout along with intermediate results See also KPRMET in Input Line 12 and KPRT in Input Une 248.

KMN Plume meander control option, as follows:

(a) -1 = Activate the Murphy and Campe building wake correction model (see parameter CONDIA in Input Line 5)

(b) 0=

Exdude plume meander consideration in the plume centerline concentration X/Q (c) 1 =

Include plume meander consideration in the plume centerline concentration XIQ Col. 20 Col. 25 KCF KWEXP Control option for recirculation correction, as follows:

(a) 0 =

No correction (b)

I =

Open terrain recirculation correction factors In Reg. Guide 1.111 (Ref. 2, Rev. 0), as built in AEOLUS-3 (c) 2 =

User-supplied correction factors via Input Line Set 24 Defaults to 2 for valleys (i.e., if KVORS<O in Col. 39-40)

Wind-speed extrapolation control option, as follows:

(a) 0 =

No extrapolation of wind speed with height (i.e. input wind speeds will be assumed to apply also at the point of release)

(b) 1 =

The following built in extrapolation:

Stabilities A, B, C, D 0.25

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 AAccident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R EVA Prepared by: Theodore A. Messier Page 22 Framatome ANP. Inc.. an AREVA and Siemens company Stabilites E, F. G :0.50 (c) 2 = User-supplied coefficients, as described in Input Line 4 Col. 30 KGX Gamma (X/Q) control option, as follows:

(a) 0 = Bypass this calculation (b).

I = Include this calculation Col. 35 KSIG Model-selection control option for the dispersion coefficients ay and at, as follows:

(a) 0 = ENTECH's model with parabolic interpolation (b)

I = Eimutis/Konicek model in XOQDOQ Col. 39-40 KVORS Sea breeze/Valley model option selection, as follows:

(a)

-1 =

Valley analysis (b) 0 = Open terrain analysis (c)

I = Sea breeze analysis Col. 44-45 KDEPL Depletion model control option:

(a) -1 = Single deposition-velocity value for all stabilities and wind speeds (see Input Une IA)

(b) 0 =

Reg. Guide 1.111 (Ref. 2, Rev. 1) depletion and deposition curves (c)

>0 Model In Meteorology & Atomic Energy (Ref. 6), with KDELP = number of wind speeds in the WSDEP and VUDEP arrays In Input Lines 10B through loX (maxl12)

Col. 50 KRAIN Wet deposition control option, as follows:

(a) 0 =

Do not evaluate wet deposition effects (b)

I =

Evaluate wet deposition effects Col. 55 NWSIN Number of wind speed groups (max 12) (see Une Set 3)

Col. 60 NEG Number of gamma energy groups in the user-specified spectrum, if any (max 16). Set NEG

-0 If Input Line Set 9 Is provided, or if KGX = 0.

Col. 61-65 INTERM Duration of intermittent releases (hours). Leave blank for the analysis of continuous or accidental releases. Set INTERM = total number of hours (not necessarily consecutive) during which intermittent releases took place, during the entire time interval represented by the joint-frequency distibution; for multi-year runs enter the annual worst-year total.

Col. 66-70 IPCT Hourly value exceedance probability for intermittent releases (percent). Leave blank for continuous or accidental releases. Set equal to 1,3, 5,10, 15, 20, 25,30, 35,40,45 or 50 for intermittent releases. Defaults to 15 if not provided, or if the selected value is greater than

50. IPCT = 2 defaults to IPCT = 1, and any value greater than 3 defaults to the nearest entry In the above list.

Col. 74-75 NMONTH Number of monthly records in the met data base which will be analyzed (maximum 240. for 20 years)

A AREVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Frainatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052821-01 Page 23 Col. 80 KTP7 Control option for transferring information to tape7 (YODA inputs) as follows (Note: Tape7 is generated only H KOPTO2):

(a)

I =

Sector, distance, description/pathway, sector-average undepleted and undecayed concentration Y(Q, sector-average depleted and decayed concentration XJQ, sector-average DIQ, and sector-average undecayed and undepleted gamma X/Q (b) 2 =

Sector, distance, description/pathway, plume centerline undepleted and undecayed concentration X/Q, plume centerline depleted and decayed concentration X/Q, plume centerline DIQ, and plume centerline undecayed and undepleted gamma X/Q If not supplied, default value is KTP7=1.

Input Line Set 3 Input Line 3A (ME103)

Col. 1-10 Col. 11-20 Col. 71-80 Input Une 3B (8E10.3)

Wind speed group definition (See notes under WSLIM(2) and WSLIM(NWSIN+1))

WSLIM(2)

WSLIM(3)

WSLIM(9)

Upper wind speed (mlse6) in the first wind speed group. Enter here the minimum wind speed acceptable as a valid observation (mlsec), corresponding to the anemometer or wind vane starting speed, whichever is larger. Hourly observations with wind speed less than WSLIM(2) will be dassified as calms with a wind speed defined by parameter WSCALM in Input Line 14) (Note: WSLIM(1) is Internally defined as 0.0)

Upper wind speed (mlsec) In the second wind speed group (Note: All hourly wind speeds WS In the range WSLIM(2) < WS < WSLIM(3) will be assigned to this group)

Upper wind speed for the eighth wind speed group (may be left blank)

Omit this Input Line if NWSIN in Input Une 2 is less than 9.

Col. 1-10 WSLIM(10)

Upper wind-speed of the ninth wind speed group WSLIM(NWSIN + 1)

Upper wind-speed of the last wind-speed group (Note: this entry should correspond to the maximum wind-speed acceptable as a valid observation, i.e., to parameter WSMAX defined in Input Une 13, after conversion to the same units)

Input Une 4 (8E10.3)

Col. 1-10 Wind-speed extrapolation data. Include this Input Une only if KWEXP = 2 (in Input Une 2). Default values for KWEXP = 1, are shown in parentheses.

WSEXP(1)

Wind-speed extrapolation coefficient for atmospheric stability A, in the form:

u(new) = ufold)'[h(new)/h(old)r" h(new) is internally set equal to 10 m for the ground-level wind speed, and to HREL (in Input Une 5) for the wind speed at the release point WSEXP(1) defaults to 0.25 if KWEXP=1.

Col. 11-20 WSEXP(2)

Coef. for stability B (0.25)

Col. 21-30 WSEXP(3)

Coef. for stability C (0.25)

A AREVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Frawnatome ANP. Inc., an AREVA and Siemens company Document ID 32-5052821-01 Page 24 Col. 3140 Col. 41-50 Col. 51.60 Col. 61-70 Inpul Une 5 (8E10.3)

Cot. 1-10 Col. 11-20 Col. 21-30 Col. 31.40 Cot. 41-50 WSEXP(4)

WSEXP(5)

WSEXP(6)

WSEXP(7)

Release-point data HREL HBLD BAREA DIAMTR VFLOW Coef. for stability D (025)

Coef. for stability E (0.50)

Coef. for stability F (0.50)

Coef. for stability G (0.50)

Height of release (m above release point grade)

Height of building adjacent to the release point (m above release-point grade)

Cross-sectional area of building adjacent to the release point causing building wake effects (m)

Effluent vent effective internal diameter (m). Set DIAMTR = 0 for ground-level releases (HREL - O), or for bypassing plume rise effects in elevated releases.

Effluent vent flow (scfm). Set VFLOW = 0 for ground-level releases, or for bypassing plume rise effects in elevated releases. Vent flow and exit velocity (EXITV) are related as follows:

VFLOW(scfn) = 1664.18'EXITV(mlsec)'DIAMTR(m) 2 Col. 51-60 Col. 61-70 Col. 71-80 OH CONDIA RVUSER Stack effluent heat content (callsec) (if >0 only buoyant plume rise will be calculated)

Equivalent diameter (m) of building causing wake effects (for use in conjunction with the Murphy and Campe building wake model, as described in Sec. 4.1.1 0 of the technical manual) (Defaults to 0.0 if KMN > 0 in Input Une 2)

Value of Rv (vent exit velocity to wind speed ratio) for the definition of plume entrainment, in lieu of the built-in Reg. Guide 1.111 model. A plume will be totally elevated (Et = 0) if Rv >

RVUSER, and at ground level (Et = 1) otherwise. Set RVUSER = 0 for the Reg. Guide model with partial entrainment.

Input Line 6 (8E10.3)

Col. 1-10 Col. 11-20 Col. 21-30 Col. 3140 Col. 41-50 General site data HINV HFMX THLFNG THLFIO SCAVCF(1:

Annual average height of inversion layer at the selected site (m above receptor grade) (see Ref. 5); defaults to 1000 m if not provided.

Maximum allowable plume centerline height (m above receptor grade) (defaults to HINV if not provided)

Noble gas half-life for decay-in-transit analysis (days). Typically set equal to 2.26 days for Xel33m. Enter0fornodecay.

Iodine half-life for decay-in-transit analysis (days). Typically set equal to 8 days for 1131.

Enter 0 for no decay.

User-specified coefficient for scavenging rate due to rainfall, based on the equation:

Scavenging rate (1lsec) = SCAVCF(1)

(RainfaU rate (mm/hr))scAVCF(

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA andSiemens company Document ID 32-5052821-01 Page 25 I

Col. 51-60 InDut Line Set 7 Input Une 7A (8E1 0.3)

Col. 1-10 Col. 71-80 Input Line 7B (8E10.3)

Col. 1-10 Col.-

Input Line Set 8 Input Line 8A (8E10.3)

Col. 1-10 Col. 71-80 Input Line 8B (8E10.3)

Col. 1-10 Col. -

Input Line Set 9 Input Line 9A (8E10.3)

Col. 1-10 Col. 11-20 Col. 21-30 Leave blank if KRAIN=0 in Input Line 2.

SCAVCF(2)

Second coefficient for the scavenging rate equation, as defined above.

Gamma energy spectra for the gamma luaus. Omit this input line set if KGX = 0, or if NEG = 0, in Input Line 2 ENGIN(1)

Midpoint energy of the first group in the gamma spectrum associated with the released radioactivity (MeV)

ENGIN(8)

Midpoint energy of the 8th group in the spectrum (if any)

Omit this input line if NEG<9 ENGIN(9).

Midpoint energy of the 9th group in tOe gamma spectrum associated with the released radioactivity (MeV)

ENGIN(NEG)

Midpoint energy of the last group In the spectrum Gamma energy spectra for the gamma Xva's. Omit this input line set if KGX= 0, or if NEG = 0 in Input Line 2.

Note: ABUND(i). where i=1 to NEG, will be Ignored if It is less than (1110,000)th of the ABUND sum.

ABUND(1)

Relative intensity of first group in the gamma spectrum corresponding to ENGIN (1) (in terms of MeVlsec).

ABUND(8)

Relative intensity of 8th group in the spectrum Omit this input line if NEG<9 ABUND(9)

Relative intensity of 9th group in the gamma spectrum corresponding to ENGIN (9)

ABUND(NEG)

Relative intensity of last group in the spectrum Release isotopics for the gamma XIQ's. Omit this Input line set if KGX = 0, or if NEG > 0 (in Input Line 2)

CONC(1)

CONC(2)

CONC(3)

Br-83 relative concentration In the effluent vent or relative release rate Br-84 relative concentration Br-85 relative concentration

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by. Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 26 I

Col. 31-40 Col. 41-50 Col. 51-60 Col. 61-70 Col. 71-80 InoUt Line 9B (8E10.3)

Col. 1-10 Col. 11-20 Col. 21-30 Col. 31-40 Col. 41-50 Col. 51-60 Col. 61-70 Col. 71-80 Input Line 9C (SE10.3)

Col. 1-10 Col. 11-20 Col. 21-30 Col. 31-40 Col. 41 50 Col. 51-60 Col. 61-70 Col. 71-80 Input Line 9D Col. 1-10 Col. 11-20 Col. 21-30 Col. 31-40 CONC(4)

CONC(5)

CONC(6)

CONC(7)

CONC(8)

CONC(9)

CONC(10)

CONC(1 1)

CONC(12)

CONC(13)

CONC(14)

CONC(15)

CONC(16)

CONC(17)

CONC(18)

CONC(19)

CONC(20)

CONC(21)

CONC(22)

CONC(23)

CONC(24)

CONC(25)

CONC(26)

CONC(27)

CONC(28)

Br-8B relative concentration Kr-83m relative concentration Kr-85m relative concentration Kr-85 relative concentration Kr-87 relative concentration Kr-88 relative concentration Kr-89 relative concentration Kr-90 relative concentraton 1-129 relative concentration 1-130 relative concentration 1-131 relative concentration 1-132 relatve concentration 1-133 relative concentration 1-134 relative concentration 1-135 relative concentration 1-135 relative concentration Xe-1316 relative concentration XE-133m relative concentration Xe-133 relative concentration Xe-135m relative concentration Xe-135 relative concentration Xe-1 37 relative concentration Xe-138 relative concentration Ar-41 relative concentration N-13 relative concentration

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by; Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 27 I

Input Une Set 10 Input Line 1OA (8E10.3)

Col. 1-10 Input Lines 108 - lOX Deposition velocity/atmospheric stability correlations. Omit this input line if KDEPL=O in Input Line 2; enter Input Line IOAif KDEPL<0; otherwise entern input lines, wheren = KDEPL, using Input Lines lOB through 10K Omit this input line if KDEPL > 0 DEPV Single deposition-velocity value, for use in conjunction with all wind speeds and all atmospheric stabilities (mlsec)

Omit these Input lines if KDEPL < 0. For KDEPL>2, AEOLUS3 applies parabolic interpolation to the WSDEP and VUDEP data provided in Input Lines lOB l 1OX to compute stability and wind-speed dependent deposition velocities corresponding to the average wind speed calculated for each stability and wind speed group combination.

If KDEPL = 2, the Interpolation applied reduces to linear. If the (deposition velocityfwind speed) ratios are stability dependent but independent of wind speed, set KDEPL = 1, along with any value for WSDEP(I).

Input Line 10B (8E10.3)

Col. 1-10 Col. 11-20 Col. 21-30 First wind speed of interest WSDEP(1)

VUDEP(1,1)

VUDEP(1,2)

Wind speed (m/sec)

(Deposition velocity/wind speed) ratio for Pasquill stability A f s b t Ratio for stability B Col. 71-80 VUDEP(1.7)

Ratio for stability G Input Line 10C (8E10.3)

Inprut Line 1OX (8E10.3)

Inout Line 11 (ABO)

Col. 1-80 Second wind speed of Interest (if any) (See Input Line I 0B for details)

Last wind speed of interest, where X stands for the (KDEPL+1)'th sequential letter in the alphabet Meteorological data Input format for the 9 parameters defined in Input Line 12 below IMT Met. data input format for the 9 parameters. Example: (5X,9F5.0)

Note:

(a)

Use only one set of parentheses (b)

Use only F formats; e.g., use F2.0 to read a 2-digit integer (c)

You must specify the formats for 9 parameters, even though the data base may contain less or more; read blank fields for parameters not available (d)

If the meteorological data files do not contain any decimals, then the F fields must be specified correctiy. For Instance, If the number 123 is the wind speed entry and corresponds to a measured wind speed of 12.3 mph., read it using the format F3.1, where the 3 is equal to the total number of digits and 1 is equal to the number of digits to the right of the decimal point; if the measured wind speed is 123 mph.,

then use the format F3.2.

Input Line 12 (1115)

Meteorological data sequence numbers in IMT (enter 0 or blank for any parameter that is not available)

Col. 5 ID)(1)

Sequence number of years in IMT

A AREVA Deternmination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by Theodore A. Messier Framaatome ANP, Inc., an ARE VA andSiemens company ID(2)

Sequence number of 'month' Document ID 32-5052821.01 Page 28 Col. 10 Col. 15 Col. 20 Col. 25 Cot. 30 Col. 35 Col. 40 Col. 45 Col. 49-50 Col. 55 Input Line 13 (8E10.

Col. 1-10 Col. 11-20 Col. 21-30 Col. 3140 Col. 41-50

.3)

ID(3)

Sequence number of 'day' ID(4)

Sequence number of 'hour' ID(5)

Sequence number of 'wind direction' ID(6)

Sequence number of 'wind speed' ID(7)

Sequence number of temperature difference' ID(8)

Sequence number of 'solar radiation'. Defaults to 0 if KVORS c 0 in Input Line 2 ID(9)

Sequence number of 'precipitation'. Defaults to 0 If KRAIN=0 in Input Line 2 KPRMET Printout control option for the hourly met data, as follows:

(a) 0 Do not include the hourly met data in the printout (b)

I Include all hourly met data In the printout (c) 2-24 =

Print the first KPRMET entries in each month (d)

>24 =

Print only every KPRMETth entry in each month KPRMET is not affected by the value selected for KPRiNT in Input Line 2. (Recommended value Is 2 or 3. Caution: Colossal output may result with KPRMET=1)

KPRJFD Printout control option for the joint frequency distributions, as follows:

(a) 0 =

Do not include the joint frequency distributions in the printout (b) 1 =

Include the joint frequency distributions in the printout Valid entries in the meteorological data base (same units as in the data base)

WDMAX Maximum wind direction acceptable as a valid observation WSMAX Maximum wind speed acceptable as a valid observation; WSMAX defaults to

\\NSLIM(NWSIN)JWSCONV] If It is less than that ratio, where WSCONV in defined in Input Line 14; i.e., preference is given to the wind-speed group definitions, and all hourly observations with wind speeds In excess of WSLIM(NWSIN) (mlsec) will be excluded from the analysis.

DTMAX Maximum temperature difference acceptable as a valid observation SUNMAX Maximum solar radiation acceptable as a valid observation RAINMX Maximum precipitation acceptable as a valid observation Input Line 14 (8E10.3)

Col. 1-10 Met data conversion factors WSCONV Factor to convert Input wind speed to mlsec

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 AAccident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by: Theodore A. Messier Page 29 Framatome ANP, Inc., an AREVA andSiemens company Col. 11-20 DTCONV Factor to convert input temperature difference to DC.

Col. 21-30 SUNCON Factor to convert solar radiation to ca/min-cm2 Col. 31-40 RAINCV Factor to convert precipitation data to mm of water Col. 41-50 WSCALM Wind speed (mrsec) to be assigned to calms (i.e., to all hourly wind speed observations which are less than WSLIM(2), the minimum wind speed acceptable as a valid observation, as defined In Input Une 3A). As specified in Reg. Guide 1.1 11, for instruments conforming with the Intent of Reg. Guide 1.23, WSCALM should be set equal to 0.5INSLIM(2); for non-conforming Instruments, WSCALM should be assigned the value of 0.1 (in/sec).

Col. 51.60 WSHITE Height of wind speed measurement (m above release-point grade), as needed for extrapolation of the wind speeds in the data base to different heights (see parameter h(old) in InputLlne4). Set WSHITE=10m if wind speed is measured at ground level; it defaults to 10 m if the user-specified value is <10 m.

Col. 61-70 DH Temperature sensor separation (m)

Col. 71-80 WDVAR Number. assigned to variable wind directions (an variable wind directions will be assigned to calms)

Input Line 15 (1615)

Sea breeze data. Omit this input line if WVORS<0.

Col. 1-5 ISEAM1 First calendar month number in sea breeze season (e.g.: enter 5 for May)

Col. 6-10 ISEAM2 Last calendar month number in sea breeze season Col. 14-15 ISEAH1 Sea breeze earliest daytime limit (hours) (LO)

Col. 19-20 ISEAH2 Sea breeze latest daytime limit (hours) (L23)

Col. 24-25 ISEASC(1)

First sea breeze downwind sector (1 for N, 2 for NNE, etc.; see Input line 20 for sequence)

Col. 29-30 ISEASC(2)

Second sea breeze downwind sector (may be 0)

I Col. 79-0 InDut Line 16 (1615)

Col. 5 Col. 10 Input Line 17 (8E10.3)

Col. 1-10 ISEASC(12) 12th sea breeze downwind sector Sea breeze data. Omit this input line if KVORS<0 ICSBM Highest stability index (and default value) In the sea breeze Joint frequency distribution that would be acceptable as a valid condition underneath the TI8L for sea breeze analysis (e.g.:

if ICSBM = 4, identified sea breeze conditions with stabilizes E, F and G in the sea breeze joint-frequency distribution will automatically default to stability D). Note that AEOLUS3 does not employ the stability index in the Identification of sea breeze conditions. If ICSBM < 0, or if ICSBM > 7, ICSBM defaults to 4.

ICSBD Default stability index below the TIBL when the TIBL elevation is below the upper delta-T sensor on the meteorological tower. If ICSBD c 0, or If ICSBD > 7, ICSBD defaults to 4.

Sea breeze data. Omit this Input line if KVORS < 0 FWSMIN Min. wind speed for sea breeze (m/sec)

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Ao Accident Analyses Using Reg Guide 1.145 and 1.194 Melhodologies A R E VA Prepared by: Theodore A. Messier Page 30 Framatome ANP. Inc., an AREVA and Siemens company Col. 11-20 FWSMAX Maximum wind speed for sea breeze Col. 21-30 SUNMIN Min. solar radiation for sea breeze (may be 0.0) (catfmin-crn?)

Col. 31-40 HINSB Depth of inversion layer during sea breeze conditions (m above receptor grade) (Defaults to IHINV in Input Une 6 if not provided, or if it is greater than HIN\\V Col. 41-50 DTHITE Height of upper level delta-T sensor (m above release-point grade)

Col. 51-60 TBLCOF(1)

User-specified coefficient for TIBL height calculation during sea breezes, based on the equation:

I Col. 61-70 a

Input Line Set 18 Input Line IBA (8E10.3)

Col. 1-10 Col. 11-20 Col. 21-30 Col. 31-40 Col. 41-50 Cot. 51-60 Col. 61-70 Col. 71-80 Input Line 18B (8E1 0.3)

Col. 1-10 Col. 11-20 Col. 21-30 Col. 31-40 Col. 41-50 Cot. 51-60 Col. 61-70 TBLCOF(2)

Sea breeze data.

DSHRP(1)

DSHRP(2)

DSHRP(3)

DSHRP(4)

DSHRP(5)

DSHRP(6)

DSHRP(7)

DSHRP(8)

DSHRP(9)

DSHRP(10)

DSHRP(1 1)

DSHRP(12)

DSHRP(13)

DSHRP(14)

DSHRP(15)

TIBL HT = TBLCOF(i)*(Dist'Solar Radi)0-5

+ TBLCOF(2)

(Max value = HINSB)

Second coefficient for the TIBL-height equation given above Omit these input lines If KVORS < 0 Distance (m) from release point to the shoreline -N sector Dist. from rel. pt to shoreline -NNE Dist from rel. pt to shoreline -NE Dist. from rel. pt to shoreline -ENE Dist from rel. pt to shoreline -E Dist. from rel. pt to shoreline -ESE Dist. from rel. pt to shoreline -SE Dist. from rel. pt to shoreline -SSE Distance (m) from release point to shoreline - S sector Dist from rel. pt to shoreline - SSW sector Dist. from rel. pt to shoreline - SW Dist. from rel. pt to shoreline - WSW Dist. from rel. pt to shoreline -W Dist. from rel. pt to shoreline -WNW Dist. from rel. pt to shoreline - NW Col. 71 -0 DSHRP(16)

Disi from rel. pt to shoreline - NNW

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatorne ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 l

Page 31 Input une Set 19 Sea breeze data. Omit these input lines if KVORS < 0 Input Line 19A (8E10.3)

Col. 1-10 DSHMT(1)

Col. 11-20 DSHMT(2)

Col. 21-30 DSHMT(3)

Col. 31-40 DSHMT(4)

Col. 41-50 DSHMT(5)

Col. 51-60 DSHMT(6)

Col. 61-70 DSHMT(7)

Col. 71-80

-DSHMT(8)

Input Line 193 (8E10.3)

Col. 1-10 DSHMT(9)

Col. 11-20 DSHMT(10)

Col. 21-30 DSHMT(11)

Col. 31-40 DSHMT(12)

Col. 41-50 DSHMT(13)

Col. 51-60 DSHMT(14)

Col. 61-70 DSHMT(15)

Col. 71-S0 DSHMT(16)

Input Line 20 (15,5X,7E110.3)

Distance (m) from met-tower to shoreline -N sector Dist from met-tower to shore. -NNE sector Dist from met-tower to shore. -NE Dist. from met-tower to shore. -ENE Dist. from met-tower to shore. -E Dist from met-tower to shore. - ESE Dist from met-tower to shore. -SE

-Dist from met-tower to shore. -SSE-Distance (m) from release point to shoreline -S sector Dist. from met-tower to shore. -SSW sector Dist from met-tower to shore. -SW Dist. from met-tower to shore. -WSW Dist. from met-tower to shore. -W Dist from met-tower to shore. -WNW DisL from met-tower to shore. - NW Dist from met-tower to shore. - NNW Valley data. Omit this input line If KVORS

. 0 Lowest delta-T stability for In-valley flows (e.g: set IDTVAL = 4 if in-valley flows occur only with stabilities D, E, F and G)

Highest hourly wind speed beyond which in-valley flows cannot be sustained (mn/sec).

Defaults to the highest wind speed defined In Input Line Set 3 if not defined.

Col. 5 IDTVAL Col. 11-20 WSVAL Inwut Une 21 (1615)

Col. 5 Valley data. Omit this input line if KVORS > 0 IVALSC(1)

Valley orientation Identification for the N sector. Set IVALSC(1) = 1 it the N sector is up-valley, IVALSC(1) = 2 if it is down-valley, or IVALSC(1) = 3 If It is in a cross-valley location. Entries not equal to 1 or 2 default to 3.

IVALSC(2)

Valley orientation ident. - NNE sector Col. 10

A ARE VA Determrination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 l

Page 32 C`l. 15 IVALSC(3)

Valley orientation ident. - NE sector Col. 20 IVALSC(4)

Col. 25 IVALSC(5)

Col. 30 IVALSC(6)

Col. 35 IVALSC(7)

Col. 40 IVALSC(8)

Cal. 45 IVALSC(9)

Col. 50 IVALSC(10)

Col. 55 IVALSC(11)

Cal. 60 IVALSC(12)

Col. 65 IVALSC(13)

Col. 70 IVALSC(14)

Col. 75 IVALSC(15)

Col. 80 IVALSC(16)

Input Line 22 (15,5X,7E10.3)

Valley orientation ident. -

Valley orientation ident -

Valley orientation ident. -

Vatley orientation ident. -

Valley orientation Ident. -

Valley orientation ident. -

Valley orientation Ident -

Valley orientation Ident.

Valley orientation Ident. -

Valley orientation ident. -

ENE sector E sector ESE sector SE sector SSE sector S sector SSW sector SW sector WSW sector W sector WNW sector NW sector NNW sector Col. 5 Col. 11-20 Col. 21-30 NACCT ACCTIM(1)

ACCTIM(2)

Time intervals for accidental releases. Omit this Input line if KOPT=1 or 2 in Input Line 2.

Typical time intervals of interest are 1, 2, 8,16,72 and 624 hrs.

Number of time values at which accident XIQ's and DI0's will be calculated (maximum 6)

First time value of interest (hours)

Second time value of Interest (hours)

Last time value of interest (hours)

Cot. -

ACCTIM(NACCT)

Input LIne 23 (20A4)

Col. 1.80 Input Line Set 24 Start of Receptor Data TlTL Any alphanumeric characters to indicate the start of receptor data. The information on this.

input tine does not appear in the printout. This input line is required whether or not there Is receptor data in the input. (Note: you may omit the receptor data sets if you are only interested in the joint frequency distributions, for instance)

Data for the first set of receptors of interest (if any). Note that each receptor set can have as many as 16 receptors, each at its own distance from the release point. However, for accidental releases, the overall site analyses will be carried out only if there is a receptor in each sector.

Input Line 24A (A1,A10)

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 A

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R EVA Prepared by. Theodore A. Messier Page 33 Framatome ANP. Inc., anAREVA and Siemens company Col. 1 ISTART Enter a " in this column; It identifies the start of a new set of receptors.

Col. 2-11 RIDENT Receptor identfication, as would apply to all the receptors in this set; e.g.: 'SITE BNDRY',

'NEARST COW, '2.0 MILES. Note that you can use only 10 characters, and that this Information will appear as a heading in the summary tables; hence, RIDENT must be unique -

to each receptor set. See Cols. 61-80 of Input Une 24B for receptor-specific information.

Input Line 24B (A3,1X1,15,F1O.3,5F8.3,2A10)

Data for first receptor in this set Col. 1-3 ISCT Downwind sector in which the receptor is located, left-justified; e.g.: N, WSW, SE Col. 5 KPRT Printout control option for this receptor, as follows:

(a) 0 =

Do not provide Intermediate results for this receptor in the printout (b) 1 =

Provide intermediate results for this receptor in the printout (such as the X/Q values for each entry in the joint frequency distribution)

Defaults to 0 if KPRINT = 0 in Input Line 2.

Col. 10 IVALOC Receptor location in the valley, as follows:

(a) 0 =

Open terrain analyses and off-valley receptors (b)

I =

Receptors in up-valley locations (c) 2 =

Receptors In down-valley locations Note that there is no relationship between this parameter and parameter IVALSC in Input tine 21. For instance, sector E may be identified as a cross-valley sector (at the release point), but the valley may meander into this sector at some distance from the release point, in which case a receptor in the E sector may Indeed be within the valley.

Col. 11-20 DIST Straight-line distance (m) from the release point to the receptor in the specified sector (Note:

For the Murphy and Campe building make model at closein receptors, enter the distance from the surface of the building causing the wake to the receptor).

Col. 21-28 HTERN Terrain height at the receptor of interest (meters above the release point grade) Note:

(a)

In line with regulatory guidance, (Reg. Guide 1.111) select the maximum terrain height between the release point and the receptor (b)

Negative terrain heights automatically exclude the receptor from the analysis; to exclude a receptor, simply do not include it In the set of receptors of interest Col. 29-36 RCF Recirculation correction factor for this receptor, this information will be used only if KCF=2 in Input Line 2. Defaults to unity If not provided.

Col. 37-44 VWIDTH Valley width at the receptor of Interest (m); defaults to 0 for off-valley receptors.

Col. 45-52 VSLOPE Valley slope (0.1 to 90 degrees) at the receptor of Interest; defaults to 0 for off-valley receptors. Note: A zero slope Is equivalent to a flat terrain.

Col. 53-60 VDIST Receptor distance (m) along the valley; leave blank only for non-valley cases. Set

A AREVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by-Theodore A. Messier Framatome ANP, Inc., an ARE'A andSiemens compa.y-Document ID 32-5052821-01 Page 34 I

Col. 61-80 DESCR DIST-5% < VDIST < DIST+5% in Input Une 24A for receptors exposed only to valley flows at all times; the XIQ's and D/r's will be based entirely on the valley models. For other distances, the open-terrain models will be used for non-valley flows. Defaults to DIST if not provided.

Receptor description (for general inf6rmation, such as pathway). Note: to produce a tape7 file in the proper format for input to YODA, the data should consist of 3 variables, PTH(1) through PTH(3), entered as 2X,2A6,F6.4 within columns 61-80 where:

PTH(1) pathway code 1, a description used by ATMOOOS to determine the active environmental pathways PTH(2) = pathway code 2 (same as above)

PTH(3) = occupancy correction factor for use in ATMODOS Input Lines 24C-24X These input lines are similar to Input Line 24B for the other receptors of interest located in different sectors. There is no need to include sectors of no interest If a sector is entered twice, the latest entry Will be used. You will run into problems if you misspell the sector name in Cols. 1-3.

Input Line Sets 25-Last Data for the remaining sets of receptors, as described for the first receptor set in Input Une Set 24. There is no limit to the number of receptors in the accident mode. For continuous and intermittent releases, the software can currently handle up to a maximum of 99 receptor sets (i.e., a maximum of 99x1 6 individual receptors, one at each of 99 distances in each sector).

A Determination of Atmospheric Dispersion Factors for Doc A

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R EVA Prepared by Theodore A. Messier Framatome ANP, Inc., an AREVA and Siemens company ATTACHMENT B: AEOLUS3 INPUTS FOR MS AND GROUND RELEASES Lne 1: Title TITLE PNPS ACCIDENT XJQ - S-YR 220-FT MET DATA - MS: ELEVATED XIQ vs distance msdiscr PNPS ACCIDENT XIQ - S-YR 220-FT MET DATA - MS: ELEVATED XIQ vs distance mrsdistsc PNPS ACCIDENT XIQ YR 220-FT MET DATA - MS: ELEVATED TO EAB mstoeab PNPS ACCIDENT X/Q YR 220-FT MET DATA - MS: ELEVATED TO EAB mstoeab2 PNPS ACCIDENT X/Q YR 220-FT MET DATA - MS: ELEVATED TO LPZ mstolpz PNPS ACCIDENT X/Q YR 220-FT MET DATA - MS: ELEVATED TO LPZ mstolpz2 PNPS ACCIDENT XIQ YR 220-FT TOWER 33-FT MET DATA - RB XJQ vs dis - rbdis PNPS ACCIDENT XIQ YR 220-FT TOWER 33-FT MET DATA - RB TO EAB - rbtoeab PNPS ACCIDENT X/Q YR 220-FT TOWER 33-FT MET DATA - RB TO EAB - rbtoeab2 PNPS ACCIDENT X/Q YR 220-FT TOWER 33-FT MET DATA - RB TO LPZ rbtolpz PNPS ACCIDENT XJO YR 220-FT TOWER 33-FT MET - TB GR-LEVEL XJQ vs dis tbdis PNPS ACCIDENT XIQ YR 220-FT TOWER 33-FT MET - TB GROUND-LEVEL TO EAB tbtoeab PNPS ACCIDENT XIO YR 220' TOWER 33' MET DATA - TB GROUND-LEVEL TO LPZ tbtolpz PNPS ACCIDENT XJQ YR 220' TOWER 33' MET DATA - YD XIQ vs distance yrddis Line 2: Program Control Options KOPT 3

Set to 3 for accident scenario KPRINT 0

Set printout control option to short printout KMN I

Set plume meander control option to include plume meander KCF 0

Set control option for recirculation correction to no correction KWEXP 1

Set wind-speed extrapolation control option to use XOQDOQ KGX 1

Set gamma CHUQ control option to Include this calculation KSIG 0

Set model-selection control option for dispersion coefficients KVORS 0

Set the sea breeze/valley model option to open terrain analys KDEPL 0

Set depletion model contol option to Reg. Guide 1.111 curve KRAIN 0

Set wet deposition control option to not evaluate wet depositi NWSIN 12 Set number of wind speed groups to twelve NEG 01 Set number of gamma energy groups In the user-specified sr cument ID 32-5052821-01 Page 35 I

in the plume centerline CHUQ's I extrapolation coefficients to the ENTECH model

,is on effects pectrum to zero (equal to 1 in 3 es to zero 1 for continuous runs (sector INTERM IPCT NMONTH KTP7 0

0 60 special cases)

Set the duration of batch releases to zero Set the hourly value exceedance probability for batch release Set number of monthly records in the met data base to 60 Sets the control option for transferring information to tape7 to average XJQ's transferred) by default

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 A

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R EVA Prepared by: Theodore A Messier Page 36 Framatome ANP. Inc., an AREVA and Siemens company Line 3A Wind Speed Group Definition WSLIM(2) 0.45 Set the upper wind speed in the first wind speed group to 0.45 rn/sec (assumes an~emometerlwind vane starting speed meets RG 1.23 criterion of 1 mph)

WSLIM(3) 1.0 Set the upper wind speed In the second wind speed group to 1.0 rn/sec WSLIM(4) 2.0 Set the upper wind speed in the third wind speed group to 2.0 rn/sec WSLIM(5) 3.0 Set the upper wind speed in the fourth wind speed group to 3.0 rn/sec WSLIM(6) 4.0 Set the upper wind speed in the fifth wind speed group to 4.0 rn/sec WSLIM(7) 5.0 Set the upper wind speed in the sixth wind speed group to 5.0 rn/sec WSLIM(8) 6.0 Set the upper wind speed in the seventh wind speed group to 6.0 rnsec WSLIM(9) 8.0 Set the upper wind speed in the eighth wind speed group to 8.0 m/sec Line 39: Wind Speed Group Definition (continued)

WSLIM(10) 10.0 Set the upper wind speed In the ninth wind speed group to 10.0 mrsec WSLIM(1 1) 13.0 Set the upper wind speed In the tenth wind speed group to 13.0 mlsec WSUM(12) 18.0 Set the upperwind speed in the eleventh wind speedgroup to 18.0 mrsec WSLIM(13) 22.4 Set the upper wind speed in the eleventh wind speed group to 22.4 n/sec Line 4: Wind-Speed Extrapolation Data Omit this fine since using built-in extrapolation coefficients (KWEXP=1)

Line 5: Release-Point Data (Refer to Appendix F of Reference 3 for basis of values.)

HREL 99.7/102.1/0.0 Set the height of release to 99.7 meters for MS to CR, 102.1 meters (335') above plant grade for MS to TSC, EAB and LPZ, set to 0.0 for ground release HBLD 0.0143.61 Set the height of the building adjacent to the release point to 0.0 for MS, 43.6 for RB, 25.9 for 25.9/0.0 TB,0.OforYard BAREA 0.0/1886.0/ Set cross-sectional area of building adjacent to 0.0 for MS, 1886.0 for RB, 2116.0 for TB, 2116.010.0 0.0 for Yard DIAMTR 0.0 Set MS effective internal diameter to 0.0 m, set to 0.0 for all other releases (no plume rise)

VFLOW 0.0 Set MS flow to 0.0 scfm (assume no credit of SGTS tow, and no plume rise); set to 0.0 for ground releases QH 0.0 Set effluent heat content to 0.0 cal/sec (bypass plume rise effects)

CONDIA

(

Leave blank equivalent diameter of building causing wake effects for use in conjunction with the Murphy and Campe building wake model to RVUSER

{ }

Leave blank Set the value of Rv (vent exit velocity to wind speed ratio) for the definition of plume entrainment to 0.0

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R EVA Prepared by: Theodore A. Messier Page 37 Framatome ANP, Inc.. an AREVA and Siemens company Line 6: General Site Data HINV 630.

Set annual average height of the inversion layer at the selected site to 630 m above receptor grade HFMX 630.

Set maximum allowable plume centerline height to 630 m above receptor grade (not applicable to ground level releases)

THLFNG 2.26 Set noble gas half-life for decay-in-transit analysis to 2.26 days THLFIO 8.0 Set iodine half-rife for decay-in-transit analysis to 8.0 days SCAVCF(1)

{

Leave first user-specified coefficient for scavenging rate due to rainfall blank (do not evaluate wet deposition effects)

SCAVCF(2)

{ }

Leave second user-specified coefficient for scavenging rate due to rainfall blank (do not evaluate wet deposition effects)

Line 7: Ganma Energy Spectra for the Gamma CHI/Qs - omit (Used value of 0.2MeV in 3 special cases)

Line 8: Gamma Energy Spectra for the Gamma CHI/Os - omit (Used value of 1.0 in 3 special cases)

Line 9: Release Isotopics for the Gamma CHI/Qs - Line omitted for the 3 cases with 0.2 MeV CONC(1) 0.0 Br-83 relative concentration set to zero CONC(2) 0.0 Br-84 relative concentration set to zero CONC(3) 0.0 Br-85 relative concentration set to zero CON C(4) 0.0 Br-88 relative concentration set to zero CONC(5) 0.0 Kr-83m relative concentration set to zero CQNC(6) 0.0 Kr-85m relative concentration set to zero CONC(7) 0.0 Kr-85 relative concentration set to zero CONC(8) 0.0 Kr-87 relative concentration set to zero CONC(9) 0.0 Kr-88 relative concentration set to zero CONC(10) 0.0 Kr-89 relative concentration set to zero CONC(11) 0.0 Kr-90 relative concentration set to zero CONC(12) 0.0 1-129 relative concentration set to zero CONC(13) 0.0 1-130 relative concentration set to zero CONC(14) 0.0 1-131 relative concentration set to zero CONC(15) 0.0 1-132 relative concentration set to zero CONC(16) 0.0 1-133 relative concentration set to zero

A Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01

-Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by: Theodore A. Messier Page 38 Framatome ANP. Inc.. an AREVA and Siemens company CONC(17) 0.0 1-134 relative concentration set to zero CONC(18) 0.0 1-135 relative concentration set to zero CONC(19) 0.0 1-136 relative concentration set to zero CONC(20) 0.0 Xe-131m relative concentration set to zero CONC(21) 0.0 Xe-1 33m relative concentration set to zero CONC(22) 1.0 Xe-133 relative concentration set to one (conservative)

CONC(23) 0.0 Xe-135m relative concentration set to zero CONC(24) 0.0 Xe-135 relative concentration set to zero CONC(25) 0.0 Xe-137 relative concentration set to zero CONC(26)..

-0.0 Xe-138 relative concentration set to zero CONC(27) 0.0 Ar-41 relative concentration set to zero CONC(28) 0.0 N-13 relative concentration set to zero tne 10: Deposition VelocitylAtmospheric Stability Correlations - omit Line 11: Meteorological Data Input Format IMT (4(i2,lx),t50,f4.0,lx,f4.1,16x,f4.1,1 x,f2Ilxf2.1) For MS Meteorological data input format for year, month, day, hour, upper level wind speed, upper level wind direction, temperature difference, precipitation, and solar radiation (4(i2,Ix),t60,f4.0,lxf4.1,6x,f4.1,lx,f2.1,lx,f2.1) ForYard, RB, TB Meteorological data input format for year, month, day, hour, lower level wind speed, lower level wind direction, temperature difference, precipitation, and solar radiation Une 12: Meteorological Data Input Sequence ID(1) 1 Sequence number of year in IMT 1D(2) 2 Sequence number of month in IMT 10(3) 3 Sequence number of day In IMT ID(4) 4 Sequence number of hour in IMT ID(5) 5 Sequence number of wind direction in IMT ID(6) 6 Sequence number of wind speed in IMT ID(7) 7 Sequence number of temperature difference in IMT ID(8) 0 Sequence number of solar radiation in IMT

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framnatome ANM. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 I

Page 39 ID(9) 0 Sequence number of precipitation in IMT KPRMET 3

Set printout control option for the hourly met data to print the first 3 entries in each month KPRJFD

{)

Set printout control option for the joint frequency distributions to not include the joint frequency distributions in the printout Line 13: Valid Entries in the Meteorological Data Base WDMAX 360.

Set the maximum wind direction acceptable as a valid observation to 360° WSMAX

99.

Set the maximum wind speed acceptable as a valid observation to 99 m/sec DTMAX

25.

Set the maximum temperature difference acceptable as a valid observation to 250C SUNMX 0.0 Set the maximum solar radiation acceptable as a valid observation to 2.0 lylmin (no data)

RAINMX -

0.0 Set the rfiaximum precipitation acceptable as a valid observation to 0.0 in/hr (no precip data)

Line 14: Meteorological Data Conversion Factors WSCONV 0.447 Set the factor to convert the input wind speed data to mrsec to 0.447 DTCONV 0.556 Set the factor to convert the input temperature difference data to 'C to 0.556 SUNCON 1.0 Set the factor to convert the input solar radiation data from langley/min to caVmin-cm2 to 1.0 RAINCV 25.4 Set factor to convert precipitation data from In/hr to mm/hr to 25.4 WSCALM 0.225 Set wind soeed to be assigned to calms to 0.225 m/sec (half of anemometer/wind vane WSHITE starting speed) 67.1110.1 Set height of wind speed measurement to 67.1 m above release-point grade for MS and 10.1 m for all others 57.0 Set the delta-temperature sensor separation to 57.Om (220-33) X 0.3048 = 57.Om

{(}

Set number assigned to variable wind directions to blank DH WDVAR Lines 15-19: Sea Breeze Data Omit these lines since the sea breeze model option is not being used (KVORS=0)

Lines 20-21: Valley Data Omit these lines since the valley model option is not being used (KVORS=0)

Line 22: Time Intervals for Accidental Releases NACCT 5/1 Use five time values for rbdis. tbdis, msdis, yrddlis, lpz cases; use one for eab cases cases 2.0 Set to two hours ACCTIM(1)

VA AiR EVA ACCTIM(2)

ACCTIM(3)

ACCTIM(4)

ACCTIM(5)

Determination of Atmospheric Dispersion Factors for Doc Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA and Siemens company 6.0 Set to six hours for rbdis, tbdis, msdis, yrddis, and Ipz cases 16.0 Set to sixteen hours for rbdis, thdis, msdis, yrddis, lpz cases 72.0 Set to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for rbdis, tbdis, msdis, yrddis, Ipz cases 624.0 Set to 624 hours0.00722 days 0.173 hours 0.00103 weeks 2.37432e-4 months for rbdis, thdis, msdis, yrddis, lpz cases ument ID 32-5052821-01 Page 40 I

Line 23: Start of Receptor Data TITL RECEPTORS Line Sets 24A-29A: Data for the Receptors of Interest ISTART 4 RIDENT SITE LPZ, SITE EAB, 200m, 400m, 60Dm, 800m, 1000m, EAB-50m, EAB-1 00m, Dis-1Om, Dis-50m, Dis-1n00m, Dis-200m, Dis-3DOm, Dis-4DOm, Dis-500m (See fles for specifics)

Line Sets 24B-29X: Data for the Receptors of Interest' ISCT N. NNE, NE,... NNW KPRT 0

Set printout control option to not provide intermediate results in the printout (except for certain sectors)

IVALOC 0

Set the receptor location in the valley to indicate open terrain analyses DIST See Section 3.0 for all cases HTERN See Section 3.0 for Main Stack case; set to zero for Reactor and Turbine Building cases RCF 0.0 Set the recirculation correction factors to zero VWIDTH 0.0 Set the valley width at the receptor of Interest to zero VSLOPE 0.0 Set the valley slope at the receptor of interest to zero VDIST 0.0 Set the receptor distance along the valley to zero DESCR See files Set the receptor description to: two-letter code for release point (MS, RB, TB, or YD),

distance, sector

A AREVA Determinafon of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by. Theodore A. Messier Frwmatome ANP. Inc.. anAREVA and Siemens companv Document ID 32-5052821-01 Page 41 I

ATTACHMENT C: COMPUTER INPUT AND OUTPUT FILE NAMES The following computer runs were carried out for this calculation:

aeolus3

1. msdiscr

2. msdistsc

3. mstoeab

4. mstolpz

5. mstoeab2

6. mstolpz2

7. rbdis

8. rbtoeab

9. rbtoeab2

10. rbtolpz

11. tbdis

12. tbtoeab

13. tbtolpz

14. yrddis Main Stack to various downwind distances (CR case)

Main Stack to various downwind distances (TSC case)

Main Stack to Exclusion Area Boundary Main Stack to Low Population Zone Main Stack to Exclusion Area Boundary (0.2MeV run)

Main Stack to Low Population Zone (0.2MeV run)

Reactor Building to various downwind distances Reactor Building to Exclusion Area Boundary Reactor Building to Exclusion Area Boundary (0.2MeV run)

Reactor Building to Low Population Zone Turbine Building to various downwind distances Turbine Building to Exclusion Area Boundary Turbine Building to Low Population Zone Yard Area to various downwind distances ARCON96

1. mscr

2. mstsc

3. rbcrl

4. rbtscl

5. rbtlcrl

6. rbUtscl

7. rbncr

8. rbntsc

9. rfpcrl

10. rfptscl

11. tbcrl

12. tbtscl Main Stack to Control Room Main Stack to Technical Support Center Reactor Building Vent to Control Room Reactor Building Vent to Technical Support Center Reactor Building Truck Lock to Control Room Reactor Building Truck Lock to Technical Support Center Reactor Building North Wall to Control Room Reactor Building North Wall to Technical Support Center Turbine Building Reactor Fuel Pump to Control Room Turbine Building Reactor Fuel Pump to Technical Support Center Turbine Building to Control Room Turbine Building to Technical Support Center

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 42 I

Listing of Files Included on the Compact Disc and Transferred to the FANP COLD Server for Archival Storage File Size Date 4.~ Thy+-...

Time File Name File Description Meteorological Data Files 693984 10/19/2004 09:27 693984 10/19/2004 09:26 692088 10/19/2004 09:27 692088 10/19/2004 09:27 692088 10/19/2004 09:27 3464232 10/19/2004 09:40 bemetO0.new bemet96.new bemet97.new bemet98.new bemet99.new be9600.met input 2000 meteorological input 1996 meteorological input 1997 meteorological input 2998 meteorological input 1999 meteorological PNPS 1996 -

2000 met data data for aeolus3 data for aeolus3 data for aeolus3 data for aeolus3 data for aeolus3 in one file for aeolus3 316224 316224 315360 315360 315360 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 09:35 09:35 09:35 09:35 09:35 pnpsO0.met pnps96.met pnps97.met pnps9B.met pnps99.met input input input input input 2000 1996 1997 1998 1999 meteorological meteorological meteorological meteorological meteorological data data data data data for ARCON96 for ARCON96 for ARCON96 for ARCON96 for ARCON96 ARCON96 5,030 566 5,030 566 5,034 566 5,034 566 5,034 566 5,034 566 566 5,034 566 5,034 5,034 566 5,034 566 5,034 566 5,034 566 Input/Output 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 Files 07:59 07:59 08:00 0'7:59 08:04 08:04 08:06 08:06 08:07 08:07 08:08 08:08 08:08 08:08 08:08 08:08 08:08 08:08 08:09 08:09 08:10 08:10 08:11 08:11 mScr.log MSCR.RSF mstsc.log MSTSC.RSF rbcrl.log RBCR1.RSF rbtlcrl.log RBTLCR1.RSF rbtltscl.log RBTLTSC1.RSF rbtscl.log RBTSCI.RSF rbncr.rsf rbncr.log rbntsc.rsf rbntsc.log rfpcrl.log RFPCR1.RSF rfptscl.log RFPTSC1.RSF tbcrl.log TBCR1.RSF tbtscl.log TBTSC1.RSF MS to CR output MS to CR input MS to TSC output

-MS to TSC input RB vent to CR output RB vent to CR input RB truck lock to CR output RB truck lock to CR input RB truck lock to TSC output RB truck lock to TSC input RB vent to TSC output RB vent to TSC input RB North Wall to CR input RB North Wall to CR output RB North Wall to TSC input RB North Wall to TSC output TB Reactor Feed Pump Area to CR output TB Reactor Feed Pump Area to CR input TB Reactor Feed Pump Area to TSC output TB Reactor Feed Pump Area to TSC input TB to CR output TB to CR input TB to TSC output TB to TSC input aeolus3 10946 324299 10947 324308 2194 81775 1945 81564 2207 87583 2953 87372 9346 290033 2122 81775 1861 81564 2160 87583 8483 256430 2176 81775 input/Output 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2004 11/02/2D04 11/02/2004 11/02/2004 11/02/2004 10/26/2004 10/26/2004 11/02/2004 11/02/2004 21/02/2004 12/02/2004 10/27/2004 10/27/2004 10/26/2004 10/26/2004 tiles 09:13 09:15 09:12 09:15 10:10 10:11 09:13 09:15 09:14 09:17 09:14 09:17 11:01 11:01 10:45 10:57 10:20 10:20 09:39 09:40 24:52 14:52 10:46 10:58 msdiscr.a3 msdiscr.out msdistsc.a3 msdistsc.out mstoeab.a3 mstoeab.out mstoeab2.a3 mstoeab2.out mstolpz.a3 mstolpz.out mstolpz2.a3 mstolpz2.out rbdis.a3 rbdis.out rbtoeab.a3 rbtoeab.out rbtoeab2.a3 rbtoeab2.out rbtolpz.a3 rbcolpz.out tbdis.a3 tbdis.out tbtoeab.a3 tbtoeab.out MS to MS to MS to VS to MS to MS to MS to MS to MS to MS to MS to MS to RB to RB to RB to RB to RB to RB to RB to RB to TB to TB to Ta to TB to various distances input file (CR case) various distances output file (CR case) various distances input file (TSC case) various distances output file (TSC case)

EAB input file EAB output file EAB input file (0.2MeV run)

EAB output file (0.2MeV run)

LPZ input file LPZ output file LPZ input file 10.2MeV run)

LPZ output file (0.2MeV run) various distances input file various distances output file EAB Input file EAB output file EAB input file (0.2MeV run)

EAB output file (0.2MeV run)

LPZ input file LPZ output file various distances input file various distances output file EAB input file EAB output file

A ARE VA Determination of Atmospheric Dispersion Factors for Accdent Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052821-01 Page 43 I

Listing of Files Included on the Compact Disc and Transferred to the FANP COLD Server for Archival Storage (continued)

File Size Date in Bytes Tine File Nae File Description aeolus3 2215 87583 9340 290042 Input/Output Files 11/02/2004 09:39 tbtolpz.a3 11/02/2004 09:40 tbtolpz.out 10/27/2004 14:09 yrddis.a3 10/27/2004 14:10 yrddis.out B3 to LPZ input file TB to LPZ output file Yard to various distances input file Yard to various distances output file Note: The time stamp for the files on the CD that were created before 10/3112004 on the system will be one hour less than shown above; this is due to the Windows XP operating system changing the time stamps of all files whenever Daylight Savings Time ends or begins. The exception to this is the ARCON96 input/output files -

since they were created on the PC on 10/26/2004, the time stamp was changed by Windows XP and this matches the time stamp for the files transferred to the FANP COLD server for archival storage.

A Determinaton of Atmospheric Dispersion Factors for Document ID 32-5052821-01 A

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by Theodore A Messier Page 44 Framatome ANP, Inc.. an AREVA and Siemens company ATTACHMENT D: ARCON96 SOFTWARE INSTALLATION TEST RECORD 2

.224t A

SOFTWARE INSTALLATION TEST RECORD AREVA Document No. (Program):

Page:

I of 1

Unique Installation Test No.: ARCON96-10082004-N&RE Installation Test Date: 10081200-4 Software Name: ARCON96 Version Tested:

1.0 Hardware Platform Tested: IBM PC Operating System Tested: WINDOWS Version Tested: XP Computer Seria No.: DVKPM11 Method of access control: EXECUTABLE FILE: SYSTEM HAS NO SOURCE CODE OR COMPILERS Testeouioment and ealibrations oed fit DD'app )

lst of bout & outout documents or elecironic files necessarv to verity the insallation test Input: exl_96.r.st ex2_96.rsf. ex3_96.rs1. ex4_96.rsf. exampe.met Output exl_'i.og. ex2_96.bog. ex3_96.og. ex4 96.Iog Installation Test Outpuc teslt.bg. testZlog. test31og. test4wJog Statement of acceptbit: Numeric va'ues in histallation test output files match those from original model output onty differences were Fun datenlme and output fde names, as expected.

Test Performner Theodore A Messier

'jlvAjK 10-08-2004 kF*. Mi. Last)

PRIITEDMPED NAUE

'SIGDTUAr DATE Franatome ANP, Inc., en AREVA and Siemens company Emcilt1ed *a RS cfse 4,,

IC-rF-CqO I

Determination of Atmospheric Dispersion Factors for AAccident Analyses Using Reg Guide 1.145 and 1.194 Methodologies A R E VA Prepared by. Theodore A. Messier Framatome ANtP, Inc., an AREI'A and Siemens company Document ID 32-5052821-01 Page 45 I

ATTACHMENT E: ARCON96 OUTPUT Main Stack to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.gov Phone: (301) 415 1232 e-mail: lab28nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 08:59:35 ARCON INPUT Number of Meteorological Data Files 5

Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (m) -

Height of upper wind instrument Cm)

Wind speeds entered as miles per hour Elevated release Release height Cm)

Building Area (m42) 10.0 67.1 102.1

.0

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP, Inc., anAREVA andSiemens company Document ID 32-5052821-01 I

Page 46 Effluent vertical velocity (mWs)

Vent or stack flow (m'3/s)

Vent or stack radius (m)

Direction..

intake to source (deg)

Wind direction sector width (deg) a Wind direction window (deg)

Distance to intake (m)

Intake height

{m)

Terrain elevation difference (m)

Output file names pnps\\mscr.log pnps\\mscr.cfd 4.06 1.70

.37 303 90 258 -

348 244.0 15.2 12.8 Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1858 flours direction in window 13383 Hours elevated plume w/ dir. in-window -

8847 flours of calm winds 12 Hours direction not in window or calm 28595 DISTRIBUTION AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO

SUMMARY

DATA BY AVERAGING INTERVAL 1

2 4

8 1.OOE-05 1.OoE-05 1.OOE-05 1.O0E-05 1.OOE-09 1.00E-09 1.OOE-09 1.00E-09

0.

2653.

3398.

4700.

7122.

0.

45.

39337.

38377.

36657.

33377.

41990.

'41775.

41357.

40544.

6.32 8.13 11.36 17.68 12 1.OOE-05 l.OOE-09 0.

9622.

449.

31040.

41111.

24.50 24 1.OOE-05 1.OOE-09 0.

15432.

1238.

24137.

40807.

40.85 96 1.OOE-05 1.OOE-09 0

0.

29969.

2194.

7721.

39804.

80.64 168 1.OOE-05 1.00E-09 0.

34166.

1728.

2824.

38718.

92.71 360 I.OOE-05 1.OOE-09 0.

36877.

488.

271.

37636.

99.28 720 1.OOE-05 1.OOE-09 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/O VALUES 3.50E-07 4.01E-07 3.70E-07 3.27E-07 2.50E-07 1.50E-07 8.17E-08 6.99E-08 5.92E-08 5.47E-08 95% X/Q for standard averaging intervals 0

2 8

1 4

to to to to to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 4.01E-07 3.02E-07 6.18E-08 5.89E-08 5.05E-08

A AREVA Deterrninaton of Atmospheric Dispersion Factors for Document ID 32.5052821-01 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A Messier Page 47 Framatome ANP. Inc., an AREVA and Siemens company HOURLY VALUE RANGE MAX X/Q 9.73E-06 5.67E-06 CENTERLINE SECTOR-AVERAGE MIN X/Q 2.14E-42 8.38E-43 NORMAL PROGRAM COMPLETION

A AR EVA Determinafon of Atmospherfc Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 48 Framalome ANP. Inc.. anAREKA and Siemenr companp Main Stack to Technical Support Center Program

Title:

ARCON96.

Developed For:

Date:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Juno 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhnrc.gov Phone: (301) 415 1232 e-mail: lab28nrc.gov Code Developer: J. V. Ramsdell Phone: 1509) 372 6316 e-mail: j ransdellpnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 08:59:57

'-++*'* ARCON INPUT **.t't'*

Number of Meteorological Data Files -

Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (m) -

Height of upper wind instrument (m) -

Wind speeds entered as miles per hour 5

10.0 67.1 Elevated release Release height (m)

Building Area (m^2)

Effluent vertical velocity (m/s)

Vent or stack flow (m^3/s)

Vent or stack radius In) 102.1

.0 4.06 1.70

.37

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an ARE VA and Siemens company Document ID 32-5052821-01 I

Page 49 Direction.. intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (n)

Intake height (m)

Terrain elevation difference (m)

Output file names pnps\\mstsc.log pnps\\mstsc.cfd Minimum Wind Speed (mis)

Surface roughness length (m)

Sector averaging constant 304 90 259 -

349 280.0 3.0 12.8

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

.00

.00 Expanded output for code testing not selected Total Hours Hours Hours Hours Hours number of hours of data processed -

43848 of missing data 1858 direction in window 13348 elevated plume w/ dir. in window -

8813 of calm winds 12 direction not in window or calm 28630 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO 1

1.OOE-04 1.0oE-08 0.

2588.

81.

39321.

41990.

6.36 2

1.00E-04 l.00E-08 0.

3060.

352.

38363.

41775.

8.17 4

l.OOE-04 1.OOE-08 0.

4088.

624.

36645.

41357.

11.39 8

1.ooE-04 l.OOE-08 0.

6202.

979.

33363.

40544.

17.71 12 1.OOE-04 1.OOE-08 0.

8775.

1284.

31052.

41111.

24.47 24 1.OOE-04 l.OOE-08 0.

14782.

1794.

24231.

40807.

40.62 96 1.OOE-04 1.OOE-08 0.

27498.

4416.

7970.

39884.

80.02 168 1.OOE-04 1.OOE-08 0.

29989.

5832.

2897.

38718.

92.52 360 1.OOE-04 1.OOE-08 0.

32476.

4889.

271.

37636.

99.28 720 I.OOE-04 1!OOE-08 0.

35775.

2947.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 4.56E-07 5.14E-07 4.73E-07 4.18E-07 3.19E-07 1.93E-07 1.04E-07 9.02E-08 7.63E-08 6.99E-08 951 X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.14E-07 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.85E-07 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8.04E-08 1 to 4 days 7.48E-08 4 to 30 days 6.46E-08 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AR EVA Determination of Atmospheric Dispersion Factors for Document ID 32*5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 50 Frarnatome ANP. Inc.. an ARE VA and Siemens companv CENTERLINE

SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 1.26E-05 7.36E-06 5.48E-43 2.12E-43

A AREVA Determination of Atmospheric Dispersion Factors for Document ID 32*505282101 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 51 Pramatome ANP. Inc., an AREVA andSiemens company Reactor Building Vent to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:04:56 ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (m}

Height of upper wind instrument (m) -

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height (m)

Building Area (m^2)

Effluent vertical velocity (m/s)

Vent or stack flow (m13/s)

Vent or stack radius (m) 48.5 1886.0

.00

A AR EVA Determination of Atmospheric Dispersion Factors for Document ID 32*505282i-01 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 52 rramatomc ANP. Inc.. an ARESIA and Siemens company Direction..

intake to source (deg)

Wind direction sector width fdeg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference (m)

Output file names pnps\\rbcrl.log pnps\\rbcrl.cfd 285 90 240 -

330 48.8 15.2

.0 Minimum Wind speed (m/s)

Surface roughness length {m)

Sector averaging constant

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

=

.00

.00 Expanded output for code testing not selected Total Hours Hours Hours Hours Hours number of hours of data processed -

of missing data a

direction in window elevated plume wI dir. in window -

of calm winds direction not in window or calm 43848 1858 14077 0

163 27750 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL XIQs

% NON ZERO 1

1.OOE-02 1.OOE-06 0.

14240.

0.

27750.

41990.

33.91 2

1.OOE-02 1.OOE-06 0.

15895.

0.

25880.

41775.

38.05 4

1.OOE-02 1.OOE-06 0.

18359.

0.

22998.

41357.

44.39 8

1.OOE-02 1.00E-06 0.

21911.

0.

18633.

40544.

54.04 12 1.00E-02 1.00E-06 0.

25373.

0.

15738.

41111.

61.72 24 1.OOE-02 1.00E-06

.. O.

31455.

0.

9352.

40807.

77.08 96 1.00E-02 1.OOE-06 0.

39226.

2.

656.

39884.

98.36 168 1.00E-02 1.OOE-06 0.

38675.

0.

43.

38718.

99.89 360 1.OOE-02 1.00E-06 0.

37636.

0.

37636.

100.00 720 1.OOE-02 1.00E-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 1.76E-03 1.68E-03 1.55E-03 1.38E-03 1.09E-03 7.44E-04 4.62E-04 4.01E-04 3.47E-04 3.35E-04 95% X/Q for standard averaging intervals 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 1.76E-03 1.25E-03 4.26E-04 3.67E-04 3.15E-04 HOURLY VALUE RANGE MAX X/Q MIN X/O

A AREVA Determinaton of Atmospheric Dispersion Factors for Document ID 32.5052821-01 l

AccidentAnalyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 53 Frarnatome ANP. Inc.. an ARE VA andSiemens company CENT ERLI NE CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 2.30E-03 1.34E-03

5. 13E-05 2.99E-05

A AR EVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 54 Framnatome ANP. Inc., an AREVA and Siemens company Reactor Bulding Vent to Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.gov Phone: (301) 415 1232 e-mail: lab2Gnrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:09:23

- - - - ARCON INPUT

Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPS0O.MET Height of lower wind instrument Cm)

Height of upper wind instrument (m)

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height (m)

Building Area (m^2)

Effluent vertical velocity (m/a)

Vent or stack flow (m'3/s)

Vent or stack radius (m)

X 48.5 1886.0

.00

A AREVA Determinaion of Atmospheric Dispersion Factors for Document ID 32-5052821-1 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by, Theodore A. Messier Page 55 Framatome ANP, Inc., an AREVA and Siemens company Direction..

intake to source (deg) a 290 Wind direction sector width (deg) 90 Wind direction window (deg) 245 -

335 Distance to intake {m) 85.3 Intake height (mi) 3.0 Terrain elevation difference (m)

.0 Output file names pnps\\rbtscl.log pnps\\rbtscl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total Hours Hours Hours Hours Hours number of hours of data processed -

43848 of missing data a

1858 direction in window 13953 elevated plume w/ dir. in window -

0 of calm winds 163 direction not in window or calm 27874 DISTRIBUTION AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs t NON ZERO

SUMMARY

DATA BY AVERAGING INTERVAL 1

2 4

8 1.00E-03 1.OOE-03 1.00E-03 1.OOE-03 1.00E-07 1.00E-07 1.OOE-07 1.OOE-07

0.

14116.

15727.

18129.

21601.

0.

27874.

26048.

23228.

18943.

41990.

41775.

41357.

40544.

33.62 37.65 43.84 53.28 12 1.OOE-03 1.OOE-07 0.

24982.

0.

16129.

41111.

60.77 24 1.OOE-03 1.OOE-07 0.

31057.

0.

9750.

40807.

76.11 1 96 1.00E-03 1.OOE-07 0.

39176.

0 O.

708.

39884.

98.22 168 1.00E-03 1.OOE-07 0.

38675.

0.

43.

38718.

99.89 360 1.00E-03 1.OOE-07 0.

37636.

0.

37636.

100.00 720 1.00E-03 1.00E-07 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 6.94E-04 6.58E-04 6.07E-04 5.42E-04 4.27E-04 2.92E-04 1.79E-04 1.55E-04 1.33E-04 1.29E-04 9g5 X/O for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 6.94E-04 4.91E-04 1.67E-04 1.41E-04 1.22E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AREVA DeterminaUon of Atmospheric Dispersion Factors for

.Document ID 32-5052821-01 1

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by Theodore A. Messier Page 56 Framatome ANP. Inc., an ARE VA and Siemens company CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 8.96E-04 5.22E-04 2.05E-05

1. 19E-05

A AREVA Determination of Atmospheric Dispersion Factors for Document ID 32-50528214)1 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier.

Page 57 Framatomc ANI.' Inc.. an AREVA and Siemens company Reactor Building Truck Lock to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 J. Y. Lie 11:00 a.m.

NRC Contacts:

J. J. Hayes L. A Brown' Phone: (301) 415 1080 e-mail: jyll~nrc.gov Phone: (301) 415 3167 e-mail: jjh~nrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United states Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:06:33

- - - - ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCo0t96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (m)

Height of upper wind instrument {m)

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height Cm)

Building Area (m12)

Effluent vertical velocity (m/s)

Vent or stack flow (m'3/3s Vent or stack radius (m)

S 6.1 1382.0

.00

A AREVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 58 rramatome ANP. Inc.. an AREJA andSiemens company Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

=

Intake height (mi)

Terrain elevation difference (m) 315 90 270 -

360 75.6 15.2

.0 Output file names pnps\\rbtlcrl.log pnps\\rbtlcrl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant By

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

=

.00

.00 Expanded output for code testing not selected Total Hours Hours Hours flours Hours number of hours of data processed -

43848 of missing data 1858 direction in window 8666 elevated plume w/ dir. in window -

0 of calm winds 142 direction not in window or calm 33182 DISTRIBUTION AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO

SUMMARY

DATA BY AVERAGING INTERVAL 1

1.00E-02 1.00E-06 0.

8808.

0.

33182.

41990."

20.98 2

1.OOE-02 1.OOE-06 0.

10414.

0 O.

31361.

41775.

24.93 4

1.OOE-02 1.OOE-06 0.

12880.

0.

28477.

41357.

31.14 8

1. OOE-02 1.00E-06 0.

16638.

0.

23906.

40544.

41.04 12 1.OOE-02 1.OOE-06 0.

20314.

0.

20797.

41111.

49.41 24 1.OOE-02 1.00E-06 0.

27401.

0.

13406.

40807.

67.15 96 1.OOE-02 1.OOE-06 0.

38856.

0.

1028.

39884.

97.42 168 1.OOE-02 1.OOE-06 0.

38666.

0.

52.

38718.

99.87 360 1.OOE-02 1.OOE-06 0.

37636.

0.

37636.

100.00 720 l.OOE-02 1.OOE-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 9.72E-04 9.55E-04 9.05E-04 8.07E-04 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 9.72E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 7.52E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2.80E-04 1 to 4 days 1.93E-04 4 to 30 days 1.61E-04

6. 46E-04 4.56E-04 2.59E-04 2.20E-04 1.95E-04 1.74E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AREVA Determinaton of Atmospheric Dispersion Factors for Document ID 32-5052821-01 1

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 59 Framatomc ANP. Inc.. an AREVA andSiemens company_

CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 1.42E-03 8.25E-04 1.38E-04 8.05E-05

A AREVA Determinaion of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 60 Framatome ANP, Inc.. an JREVA andSiemens company Reactor Building Truck Lock to Technical SupDort Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J.

Y. Lee J.

J.

Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhgnrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer:

J.

V.

Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:07:15

'**^***

ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.HET C:\\ARCoN96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C: \\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (mi n

Height of upper wind instrument (m)

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height (m)

Building Area Wm^21 Effluent vertical velocity Wmis)

Vent or stack flow (m'3/s)

Vent or stack radius (m)

W 6.1 1382.0

.00

A AREVA Determinaton of Atmospheric Dispersion Factors for Document ID 32.5052821 01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 61 Framatome ANP. Inc.. anAREVA and Siemens company I

Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake {m)

Intake height (m)

Terrain elevation difference (m}

Output file names pnps\\rbtltscl.log pnps\\rbtltscl.cfd Minimum Wind Speed Cm/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

_a 310 90 265 -

355 119.0 3.0

.0

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total flours Hours Hours Hours Hours number of hours of data processed -

43848 of missing data 1858 direction in window 9515 elevated plume w/ dir. in window -

0 of calm winds 142 direction not in window or calm 32333 I

DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

1 2

4 UPPER LIM.

1.OOE-03 1.OOE-03 1.00E-03 1

LOW LIM.

1.00E-07 1.OOE-07 1.OOE-07 I

kBOVE RANGE

0.

IN RANGE 9657.

11275.

13764.

3ELOW RANGE

0.

ZERO 32333.

30500.

27593.

TOTAL X/Qs 41990.

41775.

41357.

% NON ZERO 23.00 26.99 33.28 8

.OOE-03

.OOE-07 0.

17518.

0.

23026.

40544.

43.21 12 1.OOE-03 1.OOE-07 0.

21180.

0.

19931.

41111.

51.52 24 1.OOE-03 1.OOE-07 0.

28080.

0.

12727.

40807.

68.81 96

1. OOE-03 1.OOE-07 0.

38920.

0 O.

964.

39864.

97.58 168 1.OOE-03 1.OOE-07 0.

38666.

0.

52.

38718.

99.87 360 1.OOE-03 1.OOE-07 0.

37636.

0.

37636.

100.00 720 1.00E-03 1.00E-07 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 4.27E-04 4.21E-04 4.04E-04 3.65E-04 2.92E-04 2.07E-04 1.20E-04 1.03E-04 9.05E-05 8.OOE-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 4.27E-04 3.45E-04 1.27E-04 9.13E-05 7.39E-05 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AR EVA Determination of Atmospheric Dispersion Factors for AccidentAnalyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA andSiemens company Document ID 32-5052821-1 I

Page 62 CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

6. 07E-04 3.54E-04 6.15E-05

3. 58E-05

A AREVA Deterrmination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 63 Framatome ANP. Inc.. an AREVA and Siemens company Reactor Building North Wall to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllQnrc.gov Phone: (301) 415 3167 e-mail: jjh~nrc.gov Phone:

(301) 415 1232 e-mail: lab2gnrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdellepnl.gov Code Documentation: NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:05:24 ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCoN96\\PNPs\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPS0O.MET Height of lower wind instrument (n) a Height of upper wind instrument (n)

=

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height {m)

Building Area-1m^2)

Effluent vertical velocity (m/s)

Vent or stack flow (m'3/s)

Vent or stack radius (mn 2.0 1860.0

=

.00 3

.00 a

.00

A ARE VA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 MethodologIes Prepared by: Theodore A. Messier Page 64 Framalomc ANP. Inc., an AREVA and Siemens company Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (n)

Intake height (m)

Terrain elevation difference (m)

Output file names pnps\\rbncr.log pnps\\rbncr.cfd Minimum Wind Speed (m/s)

Surface roughness length (n)

Sector averaging constant Initial value of sigma y Initial value of sigma z a

345 90 300 -

030 45.0 15.2

.0

g

.5

.20 4.3 a

.00

=

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1858 Hours direction in window 6839 Hours elevated plume w/ dir. in window -

0 Hours of calm winds 142 Hours direction not in window or calm

=

35009 I

DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

1 2

4 UPPER LIM.

1.00E-02 1.OOE-02 1.00E-02 1

LOW LIM.

1.OOE-06 1.00E-06 1.OOE-06 1

ABOVE RANGE

0.

IN RANGE 6981.

8660.

10840.

3ELOW RANGE

0.

ZERO 35009.

33115.

30517.

TOTAL XIQs 41990.

41775.

41357.

% NON ZERO 16.63 20.73 26.21 8

.00E-02

.OOE-06 0.

14028.

0.

26516.

40544.

34.60 12 1.OOE-02 1.OOE-06 0.

17186.

0.

23925.

41111.

41.80 24 1.OOE-02 1.OOE-06 0.

23650.

0.

17157.

40807.

57.96 96 1.00E-02 1.OOE-06 0.

37404.

0.

2480.

39584.

93.78 168 1.OOE-02 1.00E-06 0.

38471.

0.

247.

38718.

99.36 360 1.OOE-02 1.OOE-06 0.

37636.

0.

37636.

100.00 720 1.OOE-02 1.OOE-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 2.36E-03 2.27E-03 2.01E-03 1.79E-03 1.44E-03 1.00E-03 5.79E-04 4.78E-04 4.22E-04 3.81E-04 95% X/Q for standard averaging intervals 0to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 2.36E-03 1.60E 03 6.10E-04 4.37E-04 3.51E-04 HOURLY VALUE RANGE MAX X/Q NIN X/Q

A AR EVA Determinatfon of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by. Theodore A. Messier Page 65 rramatomc ANP. Inc., an AREVA and Siemens company CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 3.59E-03 2.09E-03 2.86E-04 1.67E-04

A AR EVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 66 Framatome ANP. Inc.. an ARE J'A and Slemens company Reactor Building North Wall to Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjh~nrc.gov Phone: (301) 415 1232 e-mail: lab2Onrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:05:46 t****** ARCON INPUT '

Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument {m)

Height of upper wind instrument (m)

Wind speeds entered as miles per hour 5.

10.0 67.1 Ground-level release Release height (m)

Building Area (mW2)

Effluent vertical velocity (m/s)

Vent or stack flow (m^3/s)

Vent or stack radius (m) 2.0 1860.0

.00

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32.5052821401 I

Page 67 Direction.. intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference Cr5 Output file names pnps\\rbntsc.log pnps\\rbntsc.cfd Minimum Wind Speed (mis)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z 325 90 280 -

010 73.0 3.0

.0

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data

=

1858 Hours direction in window 7590 Hours elevated plume wl dir. in window -

0 Hours of calm winds 142 Hours direction not in window or calm 34258 Al B1 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

1 2

4 JPPER LIM.

1.00E-02 1.00E-02 1.00E-02 1

LOW LIM.

1.00E-06 1.00E-06 1.00E-06 I

BOVE RANGE

0.

IN RANGE 7732.

9423.

11817.

ELOW RANGE

0.

ZERO 34258.

32352.

29540.

rOTAL X/0s 41990.

41775.

41357.

I NON ZERO 18.41 22.56 28.57 8

.00E-02

.00E-06 0.

15404.

0.

25140.

40544.

37.99 12 1.00E-02 1.00E-06 0.

18934.

0.

22177.

41111.

46.06 24 1.00E-02 1.00E-06 0.

26044.

0.

14763.

40807.

63.82 96 1.00E-02 1.00E-06 0.

38543.

0.

1341.

39884.

96.64 168 1.00E-02 1.00E-06 0.

38614.

0.

104.

38718.

99.73 360

1.

005-02 1.00E-06 0.

37636.

0.

37636.

100.00 720 1.00E-02 1.00E-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 1.04E-03 1.01E-03 9.24E-04 8.18E-04 95% XIQ for standard averaging Intervals 6.55E-04 4.61E-04 2.54E-04 2.23E-04 1.96E-04 1.75C-04 0 to 2 to 8 to 1 to 4 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 hours 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 days 30 days 1.04E-03 7.44E-04 2.83E-04 1.85E-04 1.63E-04 HOURLY VALUE RANGE MAX X/Q HIN X/Q

A ARE VA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier rramatome ANP. Inc.. an AREVA and Simens company Document ID 32-5052821-01 l

Page 68 CENTERLTNE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 1.53E-03 8.91E-04

1. 47E-04 8.59E-05

A ARE VA Determinaion of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 69 Framatome ANP. Inc., anAREJ'A and Siemens company I

Turbine Building Reactor Feed Pump Area to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.n.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllGnrc.gov Phone: (301) 415 3167 e-mail: jjhQnrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:08:58

- - -** ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (m)

Height of upper wind instrument (m) -

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height (m)

Building Area (m12)

Effluent vertical velocity (m/s) vent or stack flow (m'3/s) a 18.0 406.0

.00 a

.00

A ARE VA Determinaion of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc., an AREJ'A and Siemens company Document ID 32.5052821-01 I

Page 70 Vent or stack radius (m)

.00 Direction..

intake to source (deg) 273 Wind direction sector width (deg) 90 Wind direction window (deg) 228 -

318 Distance to intake (m) 56.7 Intake height (m) a 15.2 Terrain elevation difference (n) a

.0 Output file names pnps\\rfpcrl.log pnps\\rfpcrl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

.00 a

.00 Expanded output for code testing not selected Total Hours Hours Hours Hours flours number of hours of data processed -

of missing data direction in window elevated plume w/ dir, in window of calm winds direction not in window or calm 43848 1858 13924 0

142 27924 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/0s

% NON ZERO 1

1.OOE-02 1.OOE-06 0.

14066.

0.

27924.

41990.

33.50 2

1.OOE-02 1.OOE-06 0.

16006.

0.

25769.

41775.

38.31 4

1.OOE-02 1.OOE-06 0.

18791.

0.

22566.

41357.

45.44 8

1.OOE-02 1.OOE-06 0.

22606.

0.

17938.

40544.

55.76 12 1.OOE-02 1.OOE-06 0.

26284.

0.

14827.

41111.

63.93 24 1.OOE-02 1.OOE-06 0.

32620.

0.

8187.

40807.

79.94 96 1.00E-02 1.OOE-06 0.

39386.

0.

498.

39884.

98.75 168 1.OOE-02 1.OOE-06 0.

38718.

0.

38718.

100.00 360 1.00E-02 1.OOE-06 0.

37636.

0.

37636.

100.00 720 1.0OE-02 1.OOE-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/O VALUES 1.99E-03 1.95E-03 1.89E-03 1.77E-03 1.43E-03 1.03E-03 6.46E-04 5.83E-04 5.29E-04 4.91E-04 95' X/O for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 1.99E-03 l.69E-03 6.67E-04 5.17E-04 4.67E-04 HOURLY VALUE RANGE

A ARE VA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821O 1 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 71 Framatome ANP. Inc.. an AREJ'A and Siemens company CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION MAX X/Q 2.54E-03 1.48E-03 MIN XIO 2.13E-04 1.24E-04

A AREVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821.01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared bT. Theodore A Messier Page 72 Pramatome ANP. Inc., an AREVA and Siemens company I

Turbine Building Reactor Feed Pump Area to Technical Support Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyll~nrc.gov Phone: 1301) 415 3167-e-mail:.jjhnrc.gov Phone: (301) 415 1232 e-mail: lab2Gnrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United states Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:09:21

- - - - +ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET 5

Height of lower wind instrument {m)

Height of upper wind instrument (m) -

Wind speeds entered as miles per hour 10.0 67.1 Ground-level release Release height (m)

Building Area (m12)

Effluent vertical velocity (m/s)

Vent or stack flow (m-3/s)

Vent or stack radius (m) 18.0 406.0

.00

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Framatome ANP. Inc., an ARE VA andSiemens company Document ID 32-5052821401 Page 73 Direction..

intake to source (deg) 285 Wind direction sector width (deg) 90 Wind direction window (deg) 240 -

330 Distance to intake {m) 91.4 Intake height (m) 3.0 Terrain elevation difference (m)

.0 Output file names pnps\\rfptscl.log pnps\\rfptscl.cfd Minimum Wind Speed (m/s)

.5 Surface roughness length (m)

.20 Sector averaging constant 4.3 Initial value of sigma y

.00 Initial value of sigma z

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1858 Hours direction in window 12701

-Hours elevated plume w/ dir. in window -

0 Hours of calm winds 142 Hours direction not in window or calm 29147 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER.

1 2

4 8

UPPER LIM.

l.OOE-03 1.00E-03 1.00E-03 1.OOE-03 LOW LIM.

1.00E-07 1.OOE-07 1.OOE-07 1.00E-07 ABOVE RANGE

11.

4.

2.

1.

IN RANGE 12832.

14696.

17365.

21109.

BELOW RANGE

0.

ZERO 29147.

27075.

23990.

19434.

TOTAL X/QS 41990.

41775.

41357.

40544.

M NON ZERO 30.59 35.19 41.99 52.07 95th PERCENTILE X/O VALUES 7.73E-04 7.50E-04 7.21E-04 6.73E-04 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 7.73E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6.40E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2.55E-04 1 to 4 days 1.86E-04 4 to 30 days 1.69E-04 1 12 1.00E-03 1.00E-07 0.

24718.

0.

16393.

41111.

60.13 24 1.OOE-03 1.OOE-07 0.

31260.

0.

9547.

40807.

76.60 96 1.OOE-03 1.OOE-07 0.

39255.

0.

629.

39884.

98.42 168 1.00E-03 1.OOE-07 0.

38708.

0.

10.

38718.

99.97 360 1.00E-03 1.00E-07 0.

37636.

0.

37636.

100.00 720 1.00E-03 1.00E-07 0.

38722.

0.

38722.

100.00 5.47E-04 3.94E-04 2.38E-04 2.16E-04 1.96E-04 1.78E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A ARE VA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 74 Framatome ANP, Inc., anAREVA andSiemens company_

CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 1.OOE-03 5.86E-04 8.67E-05 5.06E-05

A AREVA Determinafon of Atmospheric Dispersion Factors for Document ID 32-5052821-01 I

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by. Theodore A. Messier Page 75 Framatome ANP, Inc.. an AREVA and Siemens company Turbine Building to Control Room Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management

Date, June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Drown Phone: (301) 415 1080 e-mail: jyll~nrc.gov Phone: (301) 415 3167 e-mail: jjh~nrc.gov Phone: (301) 415 1232 e-mail: lab2Onrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdell~pnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:10:24

- - - - ARCON INPUT Number of Meteorological Data Files -

5 Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MET C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (i) -

Height of upper wind instrument (m) a Wind speeds entered as miles per hour 10.0 67.1 Ground-level release Release height (m)

Building Area (nV2)

Effluent vertical velocity (Wis)

Vent or stack flow (W^3/s)

Vent or stack radius (m) 25.9 a

2116.0

.00

A AREVA Determination of Atmosphedc Dispersion Factors for Document ID 32-5052821.01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A. Messier Page 76 Framatome ANP, Inc., an AREVA and Siemens company I

Direction..

intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference (m)

Output file names pnps\\tbcrl.log pnps\\tbcrl.cfd Minimum Wind Speed (mis)

Surface roughness length (m)

Sector averaging constant a

207 90 162 -

252 42.1 15.2

.0

.5

.20 4.3 Initial value of sigma y Initial value of sigma z

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1858 Hours direction in window 18033 Hours elevated plume wi dir. in window -

0 Hours of calm winds a

142 Hours direction not in window or calm 23815 DISTRIBUTION AVER. PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO

SUMMARY

DATA BY AVERAGING INTERVAL 1

2 4

1.O0E-02 1.00E-02 1.00E-02 1.

1.OOE-06 1.OOE-06 1.OOE-06 1.

0.

18175.

20261.

23203.

0.

23815.

21514.

18154.

41990.

41775..

41357.

43.28 48.50 56.10 8

.00E-02

.0OE-06 0.

27157.

0.

13387.

40544.

66.98 12 1.OOE-02 1.00E-06 0.

30553.

0.

10558.

41111.

74.32 24 1.OOE-02 1.00E-06 0.

35061.

0.

5746.

40807.

85.92 96 1.OOE-02 1.00E-06 0.

39566.

0.

318.

39884.

99.20 168 1.OOE-02 1.00E-06 0.

38718.

0.

38718.

100.00 360 1.00E-02 1.OOE-06 0.

37636.

0.

37636.

100.00 720 1.OOE-02 1.OOE-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 3.56E-03 3.47E-03 3.35E-03 3.22E-03 2.65E-03 1.91E-03 1.30E-03 l.19E-03 1.07E-03 9.99E-04 951 X/O for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.56E-03 2 to B hours 3.11E-03 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.26E-03 1 to 4 days 1.10E-03 4 to 30 days 9.52E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AREVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 Accident Analyses Using Reg Guide 1.145 and 1.194 Methodofogles Prepared by: Theodore A. Messier Page 77 Fraamatome ANP, Inc.. an ARE VA and Siemens company I

CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION 4.17E-03 2.43E-03 2.44E-04 1.42E-04

A AR EVA Determination of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodotogres Prepared by, Theodore A. Messier Framatome ANP. fnc.. an AREVA and Slemens comnany Document ID 32-505282i-01 Page 78 I

Turbine Building to Technrcal Supoort Center Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllnrc.gov Phone: (301) 415 3167-e-mail: jjh~nrc.gov Phone: (301) 415 1232 e-mail: lab2enrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: J;ramsdellepnl.gov Code Documentation:

NUREG/CR-6331 Rev. 1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/26/2004 at 09:11:36.

-***** ARCON INPUT Number of Meteorological Data Files Meteorological Data File Names C:\\ARCON96\\PNPS\\PNPS96.MET C:\\ARCON96\\PNPS\\PNPS97.MEIT C:\\ARCON96\\PNPS\\PNPS98.MET C:\\ARCON96\\PNPS\\PNPS99.MET C:\\ARCON96\\PNPS\\PNPSOO.MET Height of lower wind instrument (mn) -

Height of upper wind instrument (m) -

Wind speeds entered as miles per hour 5

10.0 67.1 Ground-level release Release height (m)

Building Area (In2)

Effluent vertical velocity (mfs)

Vent or stack flow Wn"3/s)

Vent or stack radius (m) 25.9 2116.0

.00

A '

AREVA Determination of Atmospheric Dispersion Factors for Document ID 32-5052821-01 l

Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by: Theodore A Messier Page 79 Framatome ANP. Inc.. an AREVA and Siemens company Direction..

intake.to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (Wn Intake height (m)

Terrain elevation difference (m)

Output file names pnps\\tbtscl.log pnps\\tbtscl.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z 256 90 211 -

301 57.9 3.0

.0

.5

.20 4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed -

43848 Hours of missing data 1858 Hours direction in window 16112 Hours elevated plume w/ dir. in window -

0 Hours of calm winds 142 Hours direction not in window or calm 25736 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER..

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO 1

1.OOE-02 1.OOE-06 0.

16254.

0.

25736.

41990.

38.71 2

1.OOE-02 l.OE-06 0.

18480.

0.

23295.

41775.

44.24 4

1.OOE-02 1.OOE-06 0.

21654.

0.

19703.

41357.

52.36 8

1.00E-02 1.OOE-06 0.

25941.

0.

14603.

40544.

63.98 12 1.OOE-02 1.OOE-06 0.

29691.

0.

11420.

41111.

72.22 24 1.OOE-02 1.OOE-06 0.

35234.

0.

5573.

40807.

86.34 96 1.00E-02 1.00E-06 0.

39555.

0.

329.

39884.

99.18 168 1.00E-02 1.OOE-06 0.

38718.

0.

38718.

100.00 360 1.00E-02 1.OOE-06 0.

37636.

0.

37636.

100.00 720 1.00E-02 1.00E-06 0.

38722.

0.

38722.

100.00 95th PERCENTILE X/Q VALUES 1.72E-03 1.71E-03 1.68E-03 1.58E-03 1.28E-03 9.05E-04 5.99E-04 5.39E-04 4.69E-04 4.35E-04 95% X/Q for standard averaging intervals.

0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 to 4 days 4 to 30 days 1.72E-03 1.54E-03 5.67E-04 4.96E-04

4. IOE-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q

A AR EVA Determinalion of Atmospheric Dispersion Factors for Accident Analyses Using Reg Guide 1.145 and 1.194 Methodologies Prepared by, Theodore A. Messier Pramatomc ANP, Inc., an AREVA and Siemens company Document ID 32.5052821-01 l

Page 80 CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETrON

2. 08E-03 1.21E-03

1. 64E-04 9.57E-05

)

20032-33 (6/2312004)

RELEASE Dp TE A

DOCUMENT RELEASE NOTICE

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NUMBER DOCUMENT TITLE CLASS (N

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N/A 32-5052036-00 Evaluation of Pilgrim Nuclear Power Station S

N Y

N 1996-2001 Meteorological Data KEYWORDS (For Informational Purposes Only)

SPECIAL REQUESTS LBL CPE Meteorology, metrose CD OF COLD_

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N/ATed Messier EXTENSION MAIL CODE SIGNATURE DATE SIGNATURE DATE 375E23

- See DRN Instructions for signature requirements.

Framatome ANP, Inc., an AREVA and Siemens company Refer to Procedure 0412-66

20697-8 (4I1I2004)

A CALCULATION

SUMMARY

SHEET (CSS)

ARE VA Document Identifier 32-5052036-00 Title Evaluation of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data PREPARED BY:

REVIEWED BY:

METHOD. 3 DETAILED CHECK 0 INDEPENDENT CALCULATION NAME Theodore A. Messier NAME John N. Hamawi SIGNATURE X

SIGNATURE g2!<Z/

4 TITLE Meteorologist DATE Tin XSF TLE C 4 Sting Radiological Eng.

DATE COST REF.

TM STATEMENT:

CENTER 41758 PAGE(S) 10-11 REVIEWER INDEPENDENCE PURPOSE AND

SUMMARY

OF RESULTS:

.. /

Purpose Evaluate the meteorological data recorded by the onsite meteorological monitoring system at Piigrim Nuclear Power Station from January 1996 through December 2001.

Results Meteorological data recorded on the 220' primary tower by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station (PNPS) from January 1996 through December 2001 were evaluated. These data were determined to be of good quality and suitable for use in atmospheric dispersion assessments.

This calculation is safety related and was prepared under the AREVA/Framatome ANP Quality Assurance Program.

THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFTY-RELATED WORK CODE/VERSIONIREV CODE/VERSION/REV metrose version 1.3 YES Z3 NO Framatome ANP, Inc., an AREVA andSiemens company Page I

of 32

22410-3 (5/10o20O4) I or2 AA DESIGN VERIFICATION CHECKLIST AREVA Document Identifier 32-5052036-00 Page 2 of 32 Title Evaluation of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data I.

Were the inputs correctly selected and incorporated into design or analysis?

El N El N/A

2.

Are assumptions necessary to perform the design or analysis activity adequately 2" Y El N al N/A described and reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?

3.

Are the appropriate quality and quality assurance requirements specified? Or, for Y

El N El N/A documents prepared per FANP procedures, have the procedural requirements been met?

4.

If the design or analysis cites or is required to cite requirements or criteria based upon

° Y

a N

t N/A applicable codes, standards, specific regulatory requirements, including issue and addenda, are these properly identified, and are the requirements/criteria for design or analysis met?

5.

Have applicable construction and operating experience been considered?

0d Y a

N f N/A

6.

Have the design interface requirements been satisfied?

° Y

[3 N.

13" N/A

7.

Was an appropriate design or analytical method used?

Y 1] N D] N/A

8.

Is the output reasonable compared to inputs?

Y.

0 N I C N/A

9.

Are the specified parts, equipment and processes suitable for the required application?

D Y E

N N/A

10.

Are the specified materials compatible with each other and the design environmental E

Y 0

N f!1N/A conditions to which the material will be exposed?

11.

Have adequate maintenance features and requirements been specified?

El Y 1Jj N NIA

12.

Are accessibility and other design provisions adequate for performance of needed a

Y E

N N/A maintenance and repair?

13.

Has adequate accessibility been provided to perform the in-service inspection expected El Y D] N Er'N/A to be required during the plant life?

14.

Has the design properly considered radiation exposure to the public and plant El Y.

0I N E3'N/A personnel?

15.

Are the acceptance criteria incorporated in the design documents sufficient to allow

° Y

ED N N/A verification that design requirements have been satisfactorily accomplished?

16.

Have adequate pre-operational and subsequent periodic test requirements been El Y 0

N UN/A appropriately specified?-.

17.

Are adequate handling, storage, cleaning and shipping requirements specified?

.. QY El N E:

N/A

18.

Are adequate identification requirements specified?

El Y C3 N 19 N/A

19.

Is the document prepared and being released under the FANP Quality Assurance 9"'Y El N

] N/A Program? If not, are requirements for record preparation review, approval, retention, etc., adequately specified?

Framatome ANP, Inc., anAREVA andSiemens company

22410-3 (5.10/2004)2 of2 IDADESIGN VERIFICATION CHECKLIST AR EVA I

Document Identifier:

32-5052036-00 Paje 3 of 32 I Comments:

Verified By:

John N. Hamawi -

(First, MI, Last)

Printed / Typed Name Signature Date Framatorme ANP, Inc., an ARE VA and Siemens company

A AREVA Evaluation of Pilgrm Nucear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP. Inc.. an ARE VA and Siemens company Document ID 32-5052036-00 Page 4 RECORD OF REVISIONS Place holder for future revisions, if any.

A AR EVA Evauaton of Pilgrm Nudear Power Station 1995-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA andSiemens company Document ID 32-5052036-00 Page 5 TABLE OF CONTENTS CALCULATION

SUMMARY

SHEET (CSS) 1 DESIGN VERIFICATION CHECKLIST.......................................................................................2 RECORD OF REVISIONS..........................................

4 TABLE OF CONTENTS..........................................

5 1.0 Purpose/Objective

.6 2.0 Assumptions and Key Assumptions

.6 3.0 Computing Environment

.6 4.0 Quality Assurance

.6 5.0 Calculations

.6 Table 1: Summary of Joint Frequency Distribution Comparison..........................................

9 Table 2: Meteorological Data Recovery Rates for the Period 1996-2001.........................................

10 6.0 Results!Conclusion.........................................

I0 7.0 References.........................................

10 Exhibit 1: BECo Meteorological Data Format...;.....;......................................................2...................... I2 Exhibit 2: PNPS Delta-Temperature Ranges (Stability Classes)..........................................

13 ATTACHMENT A: Validation of Computer Codes pnpswd and becheck.

1 4 ATTACHMENT B: COMPUTER INPUT AND OUTPUT FILES................

......................... 1 8 ATTACHMENT C: COMPUTER CODE PNPSWD LISTING.................

........................ 21 ATTACHMENT D: COMPUTER CODE BECHECK LISTING.................

........................ 26

Evauation of Pilgrrn Nuclear Power Staton Document ID 32-5052036-00 1996-2001 Meteorological Data A R EVA Prepared by: Theodore A. Messier Page 6 Framatome ANP, Inc., an.AREVA and Siemens company 1.0 Purpose/Objective Evaluate the meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station (PNPS) from January 1996 through December 2001 as requested in Entergy/Pilgrim Contract Order Number 4500534887.

2.0 Assumptions and Key Assumptions Since the base of the backup meteorological tower is not located on a natural surface, it was assumed that the data from that tower were not suitable for use in this calculation.

A key assumption is any assumption or limitation that must be verified prior to using the results and/or conclusions of a calculation for a safety-related task. There are no key assumptions in the present calculation.

3.0 Computing Environment The computer runs in this calculation Involved the use of pnpswd, becheck, and metrose and were carried out on the HP 9000/785 CPU running the HP UX B.10.20 operating system. Computer programs pnpswd and becheck were written expressly for use in this calculation and their usage is validated in Attachment A.

Computer code metrose is listed in the Framatome-ANP Computer Software Index. It is a safety-related computer code used to produce joint frequency distribution (JFD) summaries of meteorological data. There are no open software error reports for metrose; 4.0 Quality Assurance This work was performed under Framatome's Quality Assurance Program, and Framatome Procedure 0402-01 (Preparing and Processing FANP Calculations) was followed.

5.0 Calculations Meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2001 were retrieved from the Framatome-ANP (FANP) Software Control Ubrary in the form of annual files. These data had been used previously to generate annual joint frequency distribution tables for PNPS (see References 2 through 10), were in the BECo met data format (see Exhibit 1),

and included data from both meteorological towers (the 220' primary and the 160' backup). These annual data files were transmitted to PNPS and were compared to those in their possesion and were found to be identical.

Although these data had been checked previously by both PNPS and YNSD or DE&S (now AREVA/FANP), it was decided to check the data again. Computer program becheck was written to perform this data check and to determine the data recovery rates. Each of the original six annual meteorological data files were input in turn to becheck.

Program becheck checked for the following suspicious data:

Unstable delta-temperature values at night, Stable delta-temperature values all day long,

Evaluatlon of Filgrm Nuclear Power Station Document ID 32-5052036-00 A

1996-2001 Meteorological Data A R EVA Prepared by: Theodore A. Messier Page 7 Frarmatome ANP, Inc.,

an AREVA and Siemens compawy

Ambient temperature changes of ten degrees Fahrenheit or more in an hour's time, Repeating wind speed values, and

Comparison of primary towerto backup towerwind direction values.

Note that data flagged by the program were not necessarily bad data - the program simply flags data worthy of a closer look by an experienced meteorologist (indeed, the NRC computer code QA works under the same philosophy). Since the backup tower data were considered suspect and not used in this calculation, the results of the wind direction comparison were ignored. Note that while some data were flagged, it is the opinion of the author, a meteorologist with seventeen years experience, that the data are correct given the atmospheric conditions occurring when they were recorded and the location of PNPS on the shore of Massachusetts Bay.

Computer input and output file names are listed in Attachment B; copies of these files were provided on a compact disc to PNPS and were put on the FANP COLD Server for archival storage. A listing of computer code becheck is presented in Attachment D. The source code file name is becheck.f and the executable file name is becheck.e. The file sizes In bytes and the creation dateltirie are:

permissions file owner aroup size in bytes dateltime file name

-rwxrwxrwx messier eed 49245 Oct 5 14:51 becheck.e

-rw-r----- messier eed 12142 Oct 5 14:50 becheck.f As an additional check of the data, the FANP computer code metrose was used to produce a joint frequency distribution summary of the 1996-2001 meteorological data. This JFD was compared to two others produced from PNPS meteorological data from 1992 (Reference 11) and 1993 (Reference 12). This comparison of the 1996-2001 data set with historical data from the site showed good agreement. A summary of the comparison is provided in Table 1. Data recovery rates for the 1996-2001 period are provided in Table 2. Computer input and output file names are listed in Attachment B; copies of these files were provided on a compact disc to PNPS and were put on the FANP COLD Server for archival storage.

A joint frequency distribution summary of the 1996-2000 meteorological data was produced using the FANP computer code metrose. This JFD is suitable for inclusion in a PAVAN input file for use in generating atmospheric dispersion factors for accident conditions.

Visual examination of the data files indicated that the 1996 data file had wind direction values that ranged from 0 degrees to 540 degrees. The other annual files had wind direction values that ranged from 0 degrees to 360 degrees. For the sake of consistency, it was decided to convert all wind direction values from 0 to 540 degrees to 0 to 360 degrees. Computer code pnpswd was written to perform this conversion.

Each of the six annual meteorological files were input to pnpswd and two files were output in each of the six runs: the so-called banner file which lists the computer code name, version number, input file name, number of wind direction values changed, and run date, the main output file of meteorological data with wind direction values converted as necessary. Note that the computer code checked for wind direction values that were greater than 360 degrees but less than 541 degrees so as to not affect any data flagged as bad or missing (9999). The primary tower meteorological data were output by pnpswd but the backup tower meteorological data were not. Otherwise, the original BECo met data format was maintained (see Exhibit 1). Computer input and output file names are listed in Attachment B; copies of these files were provided on a compact disc to PNPS and were put on the FANP COLD Server for archival storage. A listing of computer code pnpswd is presented in Attachment C. The source code file name is pnpswd.fand the executable file name is pnpswd.e. The file sizes in bytes and the creation date/time are:

A AREVA Evaluation of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA andSiemens company Document ID 32-5052036-00 Page 8 permissions

-rwxrwxrwx

-rw-r-----

file owner 1 messier 1 messier grouD eed eed size in bytes date/time 28763 Oct 19 08:44 4518 Oct 19 08:44 file name pnpswd. e pnpswd.f Exhibit 2 presents the PNPS atmospheric stability classes as a function of delta-temperature values (degrees Fahrenheit per 187 feet). This exhibit also contains the stability class breakdown (used by the NRC in Safety Guide 23) in degrees Celsius per 100 meters, and documents the conversion from degrees Celsius per 100 meters to degrees Fahrenheit per 187 feet.

Evaluation of Pilgrm Nuclear Power Station A

1996-2001 Meteorological Data A R EVA Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32.5052036-00 Page 9 Table 1: Summary of Joint Frequency Distribution Comparison Stability 1996-2001 Class220' winds winds A

13 12.89 B

3.39 3.4 C

4.51 4.53 D

30.35 30.41 E

35.25 35.32 F

10.57 10.56 G

2.93 2.89 Major 4-7 MPH 13-18 Ws MPH Class Major SSW SSW Stability 1992 Class 33 220' winds winds A

9.89 9.88 B

3 2.99 C

3.63 3.64 D

29.25 29.44 E

32.56 32.64 F

17.49 17.38 G

4.17 4.04 Major 4-7 MPH 13-18 WS MPH Class Major SSW SSW WD Reference11 Source: Reference II Stablity1993 CSass 33' 220' winds winds A

10.1 10.23 B

3.98 4.01 C

4.95 5.09 D

37.86 37.66 E

31.69 31.91 F

9.45 9.22 G

1.96 1.88 Major 4-7 MPH 13-18 Ws MPH Class Major SSW SSW WD Reernc

_1 Source: Reference 12

Evaluaton of Pilgmn Nuclear Power Staton Document ID 32-5052036-00 A

1996-2001 Meteorological Data AR EVA Prepared by: Theodore A. Messier Page 10 Ffamatome ANP, Inc., an AREVA and Siemens company Table 2: Meteorological Data Recovery Rates for the Period 1996-2001 Data Recovery Rates Year LL Composite UL Composite 1996 96.82 95.99 1997 93.73 95.40 1998 96.71 92.05 1999 94.77 90.82 2000 91.85 91.02 2001 95.76 97.05 Six Year l

94.94 l

93.72 Average I

I Note that the composite recovery reported is the percent of time that wind speed, wind direction, and delta temperature were available simultaneously.

6.0 Results/Conclusion Meteorological data recorded on the 220' primary tower by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station (PNPS) from January 1996 through December 2001 were evaluated. These data were determined to be of good quality and suitable for use in atmospheric dispersion assessments.

7.0 References

1.

Entergy/Pilgrim Contract Order Number 4500534887.

2. AREVAJFANPCalculation BEC-0081, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First and Second Quarters 1996', dated 7/25/1996.

3. AREVANFANPCalculation BEC-0085, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions Third and Fourth Quarters 1996', dated 2/12/1997.

4. AREVA/FANPCalculation BEC-0086, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First and Second Quarters 1997", dated 8/6/1997.

5. AREVAIFANP Calculation BEC-0088, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions Third and Fourth Quarters 1997, dated 2/1011998.

6. AREVAIFANP Calculation EHS-BEC-001, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First and Second Quarters 1998", dated 8/12/1998.

7. AREVA/FANP Calculation BEC-0090, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions Third and Fourth Quarters 1998', dated 3/26/1999.

8. AREVAIFANP Calculation BEC-0091, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First, Second, Third, and Fourth Quarters 1999", dated 3120/2000.

9. AREVAIFANP Calculation BEC-0093, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First, Second, Third, and Fourth Quarters 2000", dated 4113/2001.

10. AREVA/FANP Calculation BEC-0095, Rev. 0, 'Pilgrim Station Meteorological Data Joint Frequency Distributions First, Second, Third, and Fourth Quarters 2001", dated 4116/2002.

A AREVA Evaluation of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data Prepared by. Theodore A Messier Framatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052036-00 Page 11 Ii. AREVAIFANPCalculation BEC-0063, Rev. 0, "Generation of Brookhaven National Laboratory-Format Joint Frequency Distributions, 1992M, dated 8130/1993.

12. AREVAIFANPCalculabon BEC-0070, Rev. 0, 'Generation of Brookhaven National Laboratory-Format Joint Frequency Distributions, 1993k, dated 211011994.

A Evaluation of Pilgrn Nuclear Power Station Document ID 32-505203600 1996-2001 Meteorological Data AR EVA Prepared by. Theodore A. Messier Page 12 Framatome ANP, Inc., an AREVA and Siemens company Exhibit 1: BECo Meteorological Data Format Parameter (units)

of Chars.

Columns Year 2

01-02 Month 2

04-05 Day 2

07-08 Hour 2

10-11 160 Foot Tower:

Wind Direction; 160 ft (degrees from) 4 15-18 Wind Speed; 160 ft (tenths of mph) 4 20-23 Wind Direction; 33 ft (degrees from) 4 25-28 Wind Speed; 33 ft (tenths of mph) 4 30-33 Temperature; 33 ft (degrees F) 4 35-38 Delta T; 160-33 ft (Tenths of degrees F) 4 40-43 220 Foot Tower:

Wind Direction; 220 ft (degrees from) 4 50-53 Wind Speed; 220 ft (tenths of mph) 4 55-58 Wind Direction; 33 ft (degrees from) 4 60-63 Wind Speed; 33 ft (tenths of mph) 4 65-68 Temperature; 33 ft (degrees F) 4 70-73 Delta T; 220-33 ft (Tenths of degrees F) 4 75-78 (See Attachment A of Reference 3)

A ARE VA Evaluation of Pilgrn Nuclear Power Staton 1996-2001 Meteorological Data Prepared by. Theodore A Messier Framatome ANP. Inc.. an AREVA andSiemens company Document ID 32-5052036-00 Page 13 Exhibit 2: PNPS Delta-Temperature Ranges (Stability Classes)

Stability Class Temperature Gradient '

Delta-Temperature Delta-Temperature per

°_C/1o 0 0m

°F/187' 130' A

T <= -1.9 T <=-1.95 T <-1.32 B

-1.9 > T <= -1.7

-1.95 > T <= -1.74

-1.32 > T <= -1.18 C

-1,7 > T <=-1.5

-1.74 > T <=-1.54

-1.18 > T <= -1.05 D

-1.5 > T<= -0.5

-1.54 > T<= -. 51

-105 > T <= e035 E

-0.5 > T <= 1.5

-0.51 > T <= 1.54

-0.35 > T <= 1.05 F

1.5 > T <= 4.0 1.54 > T <= 4.1 1.05 > T <= 2.79 G

>4.0 T>4.1 T>2.79

From ANSIIANS-2.5-1984, "American Standard for Determining Meteorological Informabon at Nuclear Power Sites', dated 911411984.

Evaluation of Pilgrm Nudear Power Station A1996-2001 Meteorological Data A R EVA Prepared by. Theodore A. Messier Frarnatome ANP. Inc., an AREVA and Siemens companv Document ID 32-5052036-00 Page 14 ATTACHMENT A: Validation of Computer Codes pnpswd and becheck Computer code pnpswd was written to find wind direction values greater than 360 degrees and less than 541 degrees and convert them to the appropriate value in the 0-360 degree range. In addition, pnpswd outputs only the data from the 220' tower.

To test that the code functioned properly, some data were compared between the input and output files:

Original 1996 Meteorological Data YR MN DY HR 96 1

1 0

96 1

1 1

96 1

1 2

96 1

1 3

96 1

1 4

96 1

1 5

96 1

1 6

96 1

1 7

96 1

1 8

96 1

1 9

96 1

1 10 96 1

1 11 96 1

1 12 96 1

1 13 96 1

1 14 96 1 15 96 1

1 16 96 1

1 17 96 1

1 18 96 1

1 19 96 1

1 20 96 1

1 21 96 1

1 22 96 1

1 23 BUWD BUWS BLWD BLWS BT BDT UWD-UWS LWD LWS TEMP DT 280 59 246 34 32 307 78 268 47 33 312 66 273 40 32 323 63 285 42 33 329 78 299 53 33 329 82 298 52 33 332 64 304

48 33 317 53 301 42 33 299 68 268 46 33 324 97 308 65 34 263 139 253 120 35 61 154 51 155 34 73 73 63 84 33 85 38 73 45 33 72 72 62 77 33 70 75 61 82 32 73 50 63 61 31 81 33 70 46 31 87 45 79 51 31 107 75 101 60 31 117 62 114 41 31 118 63 114 39 31 137 84 133 44 31 146 78 131 41 31 21 15 8

3 3

3 2

1

-1

-7

-6

-5

-4

-3

-5

-3

-4

-5

-4

-2

-2 299 78 241 310 106 276 310 89 265 331 94 265 329 105 282 328 103 295 328 81 299 304 89 278 311 101 269 327 126 295 365 181 353 409 178 391 425 142 425 437 102 426 424 131 427 416 132 409 422 120 418 428 114 422 441 94 427 456 100 456 459 75 204 473 85 179 478 116 100 493 121 134 32 41 35 33 42 37 33 50 28 53 93 89 74 62 76 72 65 78 49 52 27 37 47 31 33 25 32 23 33 10 33 16 33 9

32 12

.33 4

33 1

33

-2 36

-16 35

-13 35

-12 34

-12

34.

-11 34

-11 33

-11 32

-12 32

-10 32

-9 32

-7 32

-7 Processed 1996 Meteorological Data YR MN DY HR 96 1

1 0

96 1

1 1

96 1

1 2

96 1

1 3

96 1

1 4

96 1

1 5

96 1

1 6

96 1

1 7

96 1

1 8

96 1

1 9

96 1

1 10 96 1

1 11 96 1

1 12 96 1

1 13 96 1

1 14 96 1

1 15 96 1

1 16 UWD UWS LWD 299 78 241 310 106 276 310 88 265 331 93 265 329 105 282 328 103 295 328 81 299 304 88 278 311 101 269 327 126 295 5

181 353 49 177 31 65 141 65 77 101 66 64 131 67 56 131 49 62 120 58 LWS 32 40 35 32 41 37 32 50 27 53 93 88 74 61 75 71 65

- TEMP DT 33 25 32 22 33 10 33 16 33 8

32 12 33 4

33 1

33

-2 36

-16 35

-12 35

-12 34

-11 34

-11 33

-11 32

-12

A AR EVA Evaluation of Pilgrrn Nuclear Power Station 1996-2001 Meteorological Data Prepared by. Theodore A. Messier Framatome ANP. Inc.. an ARE VA and Siemens comranv Document ID 32-5052036-00 Page 15 96 96 96 96 96 96 96 1

I 1

1 1

117 118 1 19 120 121 122 123 68 81 96 99 113 118 133 113 93 100 75 85 116 121 62 67 96 204 179 100 134 78 49 51 27 37 46 30 32 32 32 32 32 32 32

-10

-8

-6

-6 Original 2000 Meteorological Data YR MN DY HR 00 12 28 00 00 12 28 01 00 12 28 02 00 12 28 03 00 12 28 04 00 12 28 05 00 12 28 06 00 12 28 07 00 12 28 08 00 12 28 09 00 12 28 10 00 12 28 11 00 12 28 12 00 12 28 13 00 12 28 14 BUWD BUWS BLWD BLW 229 251 260 255 228 227 222 215 238 245 9999 9999 9999 9999 287

-10

-11

-11 9999 9 9999 9 9999 9 9999 9

-10 260 278 284 280 267 265 254 254 274 281

'999

'999 999 297 67 109 105 109 64 56 50 59 108 120 9999 9999 9999 9999 107 S BT 20 20 20 20 19 18 17 18 19 21 9999 9999 9999 9999 22 BDT

-4

-5

-6

-5

-3

-4

-8

-10 9999 9999 9999 9999

-15 UWD 263 273 278 277 270 266 261 259 267 9999 9999 286 296 288 293 UWD 263 273 278 277 270 266 261 259 267 9999 9999 286 296 288 293 UWS 173 221 224 221 163 160 155 168 205 9999 9999 242 259 262 244 UWS 172 221 223 221 162 160 155 167 205 9999 9999 242 258 262 243 LWD 258 265 268 268 258 255 251 252 263 9999 9999 279 291 282 286 LWD 258 265 268 268 258 255 251 252 263 9999 9999 279 291 282 286 LWS 73 89 91 93 66 68 59 65 90 9999 9999 99 104 107 98 LWS 73 88 91 93 65 68 59 65 90 9999 9999 98 103 106 98 Processed 2000 Meteorolooical Data YR MN DY HR 0 12 28 0

0 12 28 1

0 12 28 2

0 12 28 3

0 12 28 4

0 12 28 5

o 12 28 6

0 12 28 7

0 12 28 8

0 12 28 9

0 12 28 10 0 12 28 11 0 12 28 12 0 12 28 13 0 12 28 14 TEMP 22 22 21 21 20 20 19 19 20 9999 !

9999 t 24 24 22 22 TEMP 22 22 21 21 20 20 19 19 20 9999 !

9999 c 24 24 22 22 DT

-6

-7

-5

-7

-11 9999 9999

-25

-22

-19 DT

-6

-5

-6

-11

)999 i999

-25

-22

-18 From this it can be seen that computer code pnpswd changed only the appropriate wind direction values and did not output the 160' towerdata. (Note that the one-digit vs. two-digit output of the year 2000 is not significant as long as the one-digit is right-justified.)

A ARE VA Evaluation of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data Prepared by. Theodore A. Messier Framatome ANP, Inc.. an AREVA andSiemens company Document ID 32-5052036-00 Page 16 Computer code becheck was written to find suspicious meteorological data values. In addition, becheck output Computer code becheck was written to find suspicious meteorological data values. In addition, becheck output the meteorological data recovery.

To test that the code functioned properly, some data were compared from the input and output files:

2001 Meteorological Data YR MN DY HR BUWD BUWS BLWD BLWS BT 01 01 01 01 01 01 01 01 01 01 01 11 11 11 11 11 11 11 11 11 11 11 22 22 22 22 22 22 22 23 23 23 23 17 18 19 20 21 22 23 00 01 02 03 191 206 323 67 89 130 105 31 29 39 44 58 51 16 18 30 44 25 27 43 90 104 172 175 211 211 201 194 216 234 213 347 49 15 11 13 17 16 21 10 16 8

53 89 44 44 40 40 40 41 41 40 40 44 47 BDT 37 28 54 66 65 58 53 46 51 20

-8 UWD 192 220 253 66 85 108 98 55 45 45 46 UWS 68 91 48 31 43 52 46 45 69 96 106 LWD 210 199 277 227 165 171 262 260 289 30 42 LWS 9

12 3

3 3

8 12 TEMP 45 45 43 44 45 45 44 43 44 45 46

- DT 21 19 23 19 16 21 23 26 16 8

-3 Wind Speed Values Flagged BECO PRIMARY TOWER SUSPECT WIND SPEED DATA 1 11 22 23

.3 LL WS SENSOR MAY BE STUCK This indicates that repeating wind speed values were flagged.

1997 Meteorological Data YR MN DY HR BUWD BUWS BLWD BLWS BT 97 2 27 22 227 172 216 101 55 97 2 27 23 307 123 291 78 40 97 2 28 0

307 83 295 53 41 BDT

_9

-15

-12 UWQ 236 310 309 UWS 216 149 110 LWD 217 274 278 LWS 84 46 37 TEMP 55 40 41 DT

-3 3

4 Ambient Temperature Values Flagged BECO PRIMARY TOWER SUSPECT TEMP. DATA 97 1

9 12

44. TEMP. CHANGE > 10 DEG F !!!!!

97 1

9 13

32. TEMP. CHANGE > 10 DEG F !!!!!

97 2 27 23

40. TEMP. CHANGE > 10 DEG F !!

97 4

2 11

42. TEMP. CHANGE > 10 DEG F !!

97 7 18 21

66. TEMP. CHANGE > 10 DEG F !!!!!

97 9 20 19

62. TEMP. CHANGE > 10 DEG F !!

97 11 17 7

26. TEMP. CHANGE > 10 DEG F !!

This indicates that ambient temperature changes equal to or greater than ten degrees Fahrenheit were flagged.

A AREVA Evaluaton of Pilgrm Nuclear Power Station 1996-2D01 Meteorological Data Prepared by. Theodore A. Messier Framatome ANP. Inc.. an AREVA andSiemens company Document ID 32-5052036-00 Page 17 2001 Meteorological Data YR MN DY HR BUWD BUWS BLWD BLWS BIT 01 01 20 18 73 9999 57 216 33 01 01 20 19 68 9999 52 237 32 01 01 20 20 74 9999 54 227 32 01 01 20 21 64 9999 45 252 31 01 01 20 22 63 9999 48 258 31 01 01 20 23 61 9999 46 270 31 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 00 01 02 03 04 05 06 07 08 09 10 11 12 13 14 15 16 17 18 19 20 21 22 23 261 265 264 269 269 275 281 299 9999 9999 9999 9999 9999 350 345 339 353 348 337 325 324 330 351 359 163 176 167 161 161 169 132 108 9999 9999 9999 9999 9999 135 99 129 188 209 142 167 167 160 154 111 252 255 254 255 262 272 279 302 9999 9999 9999 9999 9999 324 327 349 348 348 326 314 310 315 343 340 92 101 99 87 79 84 79 78 9999 9999 9999 9999 9999 53 42 60 79 95 67 77 90 90 81 51 76 75 75 74 74 75 76 78 9999 9999..

9999 9999 9999 76 77 78 76 74 74 75 75 73 70 67 BDT

-14

-13

-12

-13

-12

-11

-2

-1

-2

-3

-5

-10

-13 9999 9999 9999 9999 9999 5

1 13 20 23 18 14 9

8 12 5

UWo 49 45 48 37 40 37 260 263 263 268 268 275 280 295 9999

.335 335 336 340 339 331 324 339 333 322 314 316 322 341 352 UWS 272 270 278 273 307 283 210 219 219 223 223 233 194 165 9999 221 181 131 225 201 148 206 226 257 199 226 213 197 204 160 LWD 42 39 42 35 37 33 9999 9999 9999 9999 9999 9999 9999 9999 9999 340 332 340 333 299 295 319 306 319 289 299 290 301 339 337 LWS 118 126 122 132 141 133 76 81 79 77 75 71 59 50 9999 41 40 34 40 38 30 36 35 41 29 42 39 38 37 24 TEMP 34 33 33 33 33 33 9999 9999 9999 9999 9999 9999 9999 9999 9999 75 75 77 77 75 76 78 75 73 72 73 72 71 68 65 DT

-21

-19

-17

-12

-17

)999

)999 3999

)999

)999 9 999

)999 25 25

-3 24 32 20 28 31 41 44 34 30 25 27 31 Delta-Temperature Values Flaged BECO PRIMARY TOWER SUSPECT DELTA-T DATA 1

1 20 20

-1.7 UNSTABLE VALUE AT NIGHT 1

1 20 22

-1.7 UNSTABLE VALUE AT NIGHT 1

1 20 23

-1.7 UNSTABLE VALUE AT NIGHT 1

6 28 STABLE ALL DAY This indicates that delta-temperature values in the unstable range during the night were flagged and that days in which the delta-temperature values were in the stable range all day were flagged.

A Evaluation of Pilgrm Nudear Power Station 1996-2001 Meteorological Data A R EVA Prepared by. Theodore A Messier Framatome ANP. Inc.. an AREVA and Siemens company ATTACHMENT B: COMPUTER INPUT AND OUTPUT FILES.

The following computer runs were carried out for this calculation:

becheck Document ID 32-5052036-00 Page 18 1996 1997 1998 1999 2000 2001 pnpsw 1996 1997 1998 1999 2000 2001 PNPS 1996 meteorological data; input file bemet96; output files 1996.dr, 1996.ws, 1996.dt, 1996.at, 1996.wd PNPS 1997 meteorological data; input file bemet97; output files 1997.dr, 1997.ws, 1997.dt, 1997.at, 1997.wd PNPS 1998 meteorological data; input file bemet98; output files 1998.dr, 1998.ws, 1998.dt, 1998.at, 1998.wd PNPS 1999 meteorological data; input file bemet99; output files 1999.dr, 1999.ws, 1999.dt, 19°9.at, 1999.wd PNPS 2000 meteorological data; input file bemet96.new; output files 2000.dr, 2000.ws, 2000.dt, 2000.at, 2000.wd PNPS 2001 meteorological data; input file bemet96.new; output files 2001.dr, 2001.ws, 2001.dt, 2001.at, 2001.wd d

PNPS 1996 meteorological data; input file bemet96.new; output files pnpswd.banner.96 and bemet96.new PNPS 1997 meteorological data; input file bemet97.new; output files pnpswd.banner.97 and bemet97.new PNPS 1998 meteorological data; input file bemet98.new; output files pnpswd.banner.98 and bemet98.new PNPS 1999 meteorological data; input file bemet99.new; output files pnpswd.banner.99 and bemet99.new PNPS 2000 meteorological data; input file bemet0O.new; output files pnpswd.banner.00 and bemetOO.new PNPS 2001 meteorological data; input file bemet0l.new; output files pnpswd.banner.01 and bemetOl.new

A AREVA Evaluation of Pilgrm Nudear Power Station 1996-2001 Meteorological Data.

Prepared by: Theodore K Messier Framatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052036-00 Page 19 metrose Lower Level Upper Level Lower Level Upper Level PNPS 1996-2001 meteorological data (33' wind speed and direction); input files beinl9601.m3 and bemet96.new, bemet97.new, bemet98.new, bemet99.new, bemetOO.new, bemetOl.new; output file beI19601.out PNPS 1996-2001 meteorological data (220' wind speed and direction); input files beinu9601.m3 and bemet96.new, bemet97.new, bemet98.new, bemet99.new, bemetOO.new, bemetOl.new, output file beul9601.out PNPS 1996-2000 meteorological data (33' wind speed and direction); input files beinl9600.m3 and bemet96.new, bemet97.new, bemet98.new, bemet99.new, bemetOO.new; output file be119600.out PNPS 1996-2000 meteorological data (220' wind speed and direction); input files beinu9600.m3 and bemet96.new, bemet97.new, bemet98.new, bemet99.new, bemetOO.new; output file beul9600.out

A AREVA Evaluation of Pjigrm Nuclear Power Staton 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP, Inc., anAREVA and Siemens company Document ID 32-5052036-00 Page 20 Listing of Files Included on the Compact Disc and Transferred to the FANP COLD Server for Archival Storage File Size Date in 9vtes Time File Name File Description 169 Oct 169 Oct 169 Oct 169 Oct 169 Oct 169 Oct 693984 Oct 693984 Oct 692088 Oct 692088 Oct 696171 Oct 693984 Oct 692089 Oct 692088 Oct 692089 Oct 692088 Oct 692088 Oct 692088 Oct 4518 Oct 548 'Oct 427 Oct 16654 Oct 839828 Oct 145 Oct 398 Oct 427 Oct 6010 Oct 80603 Oct 99 Oct 1148 Oct 427 Oct 5242 Oct 126077 Oct 53 Oct 748 Oct 427 Oct 16466 Oct 164502 Oct 99 Oct 548 Oct 427 Oct 16778 Oct 72812 Oct 53 Oct 348 Oct 427 Oct e254 Oct 115212 Oct 99 Oct 12142 Oct 101 Oct 497 Oct 501 Oct 496 Oct 501 Oct 85036 Oct 95256 Oct 85036 Oct 95256 Oct 17230 Oct 17230 Oct 19 09:27 pnpswd.banner.00 19 09:27 pnpswd.banner.01 19 09:26 pnpswd.banner.96 19 09:27 pnpswd.banner.97 19 09:27 pnpswd.banner.98 19 09:27 pnpswd.banner.99 4 09:53 bemetOO 19 09:27 bemetOO.new 4 09:53 bemetOl 19 09:27 bemetOl.new 4 09:53 bemet96 19 09:26 bemet96.new 4 09:54 bemet97 19 09:27 bemet97.new 4 09:54 bemet98 19 09:27 bemet98.new 4 09:54 bemet99 19 09:27 bemet99.new

.4 16:01 pnpswd.tf 7 11:25 1996.at 7 11:25 1996.dr 7 11:25 1996.dt 7 11:25 1996.wd 7 11:25 1996.ws 7 11:25 1997.at 7 11:25 1997.dr 7 11:25 1997.dt 7 11:25 1997.wd 7 11:25 1997.ws 7 11:25 1998.at 7 11:25 1998.dr 7 11:25 1998.dt 7 11:25 1998.wd 7 11:25 1998.ws 7 11:24 l999.at 7 11:24 1999.dr 7 11:24 l999.dt 7 11:24 l999.wd 7 11:24 1999.ws 7 11:24 2000.at 7 11:24 2000.dr 7 11:24 2000.dt 7 11:24 2000.wd 7 11:24 2000.ws 5 15:49 2001.at 5 15:49 2001.dr 5 15:49 2001.dt 5 15:49 2001.wd 5 15:49 2001.ws 5 14:50 becheck.f 7 11:24 movem 20 09:34 beinl9600.m3 4 15:44 beinl9601.m3 20 09:34 beinu9600.m3 4 15:45 beinu9601.m3 20 09:38 bell9600.out 19 09:39 bell9601.out 20 09:39 beul9600.out 19 09:39 beul9601.out 20 09:38 metrose.xoqdoq.jfd.10680 20 09:39 metrose.xoqdoq.jfd.10693 banner output for pnpswd using 2000 data banner output for pnpswd using 2001 data banner output for pnpswd using 1996 data banner output for pnpswd using 1997 data banner output for pnpswd using 1998 data banner output for pnpswd using 1999 data original 2000 met data 2DOO met data from pnpswd original 2001 met data 2001 met data from pnpswd original 1996 met data 1996 met data from pnpswd original 1997 met data 1997 met data from pnpswd original 1998 met data 1998 met data from pnpswd original 1999 met data 1999 met data from pnpswd source code for pnpswd ambient temperature flags for 1996 data recovery for 1996 delta-temperature flags for 1996 wind direction flags for 1996 (not used) wind speed flags for 1996 ambient temperature flags for 1997 data recovery for 1997 delta-temperature flags for 1997 wind direction flags for 1997 (not used) wind speed flags for 1997 ambient temperature flags for 1998 data recovery for 1998 delta-temperature flags for 1998 wind direction flags for 1998 (not used) wind speed flags for 1998 ambient temperature flags for 1999 data recovery for 1999 delta-temperature flags for 1999 wind direction flags for 1999 (not used) wind speed flags for 1999 ambient temperature flags for 2000 data recovery for 2000 delta-temperature flags for 2000 wind direction flags for 2000 (not used) wind speed flags for 2000 ambient temperature flags for 2001 data recovery for 2001 delta-temperature flags for 2001 wind direction flags for 2001 (not used) wind speed flags for 2001 source code for becheck unix script file used to rename becheck output files metrose 33' input file for 1996-2000 data metrose 33' input file for 1996-2001 data metrose 220' input file for 1996-2000 data metrose 220' input file for 1996-2001 data metrose 33'. output file for 1996-2000 data metrose 33' output file for 1996-2001 data metrose 220' output file for 1996-2000 data metrose 220' output file for 1996-2001 data 33' JFD for input to PAVAN 220' JFD for input to PAVAN Note: The time stamp for the files on the CD will be one hour less than shown above; this is due to the Windows XP operating system changing the time stamps of all files whenever Daylight Savings Time ends or begins.

A AR EVA Evaluaton of PlIgrm Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA andSiemens company Document ID 32-5052036-00 Page 21 ATTACHMENT C: COMPUTER CODE PNPSWD LISTING HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 08:44:58 2004 pnpswd.f Page 1

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 C

C C

program pnpswd This program reads PNPS meteorological data from the primary tower in it's "old" format (BECo) and assumes that headers have been insert at the beginning of each month that indicate the number of hours of data in the month (i3 format).

It checks for wind direction values that are > 360 degrees.

The data are output with WD values all set to 360 or less in value; this is accomplished by subtracting 360 from any WD value that is > 360.

Version 1.0 Written 10-04-2004 T.A. Messier FANP.

Variable List yr dy hr numhrs ival integer integer integer integer integer integer year month day hour number of hours of data in month number of WD values changed 27 c 28 c Variables uwd through delt are real values but written in the data f ile 29 c as if they were integers; therefore, they will be read/written as in tegers 30 c uwd real 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 c

C uws C

lwd e North) c lws c

temp C

delt c

c infile c

outfil c

banner le name, c

c today c

real real real real real character character character character 220' wind direction (degrees from True North) 220' wind speed (MPH) 33' wind direction (degrees from Tru 33' wind speed (MPH) ambient air temperature (degrees F) delta temperature (degrees F/187')

input file name output file name banner output; date of run, input fi number of WD values changed date of run integer yr,mn,dy,hr,numhrs,ival integer uwd,uws,lwd,lws,temp,delt character*15 infile,outfil,banner character*9 today

A AR EVA Evaluaton of Pilgrm Nudear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Framatome ANP, Inc.,

an.AREVA and Siemens company Document ID 32-5052036-00 Page 22 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 08:44:58 2004 pnpswd.f Page 2

50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 data outfil/'pnpswd.out'/

data banner/ 'pnpswd.banner'/

data ival/O/

c Ask for input file name print *," Enter input file name read(*,2)infile 2

format(al5) c Open input file open (25, file-infile) c Open output file open(26,file-outfil)

C C

C 3

Open banner file open(36,file-banner)

Get date of run call date(today)

Write code info to banner file write(36,3)today format(' FANP Computer Code pnpswd

',alO,/,/)

version 1.0',/,/'

Date of Run:

c Write input file name to banner file write(36,4)infile 4

fonnat(/,'

Input file name:

',al5,/,/)

c Read number of hours of hourly data in the month c Upon reaching end of all months of data, goto 100 6

read(25,7,end=100)numhrs 7

format(i3) c Output numhrs write(26,7)numhrs c Loop through month of hourly data do 20 i-l,numnhrs read(25,9)yr,mn,dy,hr,uwd,uws,lwd,lws,ternp,delt 9

format(4(i2,lx),t50,i4,t55,i4,t60,i4,t65,i4,t70,i4,t75

,i4) c Check if wd is greater than 360 degrees; if so, subtract 360 c Increment ival when WD values are changed if((uwd.gt.360).and.(uwd.1t.541))then uwd-uwd-360 ival-ival+l else endif if((lwd.gt.360).and.(lwd.1t.541))then

A AR EVA Evaluaton of Pigrn Nuclear Power Station 1996-2001 Meteorological Data Prepared by. Theodore A. Messier Framnatome ANP. Inc.. an AREVA and Siemens companv Document ID 32-5052036-00 Page 23 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 08:44:58 2004 pnpswd.f Page 3

103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 lwd-lwd-360 ival-ival+l else endif c Output the hourly data write(26,15)yr,mn,dy,hr,uwd,uws,lwd,lws,temp,delt 15 fornat(4(i2.2,lx),t50,i4,t55,i4,t60,i4,t65,i4,t70,i4,t75,i4) 20 continue c If still data to read, then goto line 6 goto 6 100 continue c Write number of changed WD values to banner file write(36,105)ival 105 format('

Number of WD values changed by program pnpswd is:

',i6, stop 'PNPS met data written to file named pnpswd.out' end Compilation statistics for procedure: pnpawd Number of-errors:

Procedure number:

I 0

Number of Warnings:

0 Accumulated number of source lines read:

125

A AREVA Evaluaton of Pilgrrn Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Franatome ANP, Inc., an AREVA andSiemens company Document ID 32-5052036-00 Page 24 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 pnpswd.f 08:44:58 2004 Page 4

CROSS REFERENCE LISTING:

Symbol File Function Line banner date delt dy hr i

infile ival lwd lws mn numhrs outfil pnpswd()

temp today uwd uws yr pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd.f pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd pnpswd ppnpswd pnpswd pnpswd pnpswd pnpswd

47 69

46

45

45 89

47

45

46

46

45

45

47

1

46-

48

46

46

45 51 66 91 91 91 56 52 91 91 91 82 50 91 69 91 91 91 109 109 109 60 77 99 104 120 102 103 109 109 109 86 89 63 109 72 97 98 109 109 109 SYMBOL TABLE LISTING:

Symbol Class Type Offset/Size banner date ()

delt dy hr i

infile ival lwd lws mn numhrs outfil pnpswd()

temp today uwd uws yr Variable Procedure: intrinsic Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Procedure: this func.

Variable Variable Variable Variable Variable Character Subroutine Integer*4 Integer*4 Integer*4 Integer*4 Character Integer*4 Integer*4 Integer*4 Integer*4 Integer*4 Character Subroutine Integer*4 Character Integer*4 Integer*4 Integer*4 Data: DS$pnpswd+O Local: SP -144 Local: SP -172 Local: SP -168 Local: SP -188 Local: SP -344 Data: SD$pnpswd+O Local: SP -156 Local: SP -152 Local: SP -176 Local: SP -192 Data: DS$pnpswd+16 Local:

Local:

SP SP SP SP SP

-148

-204

-164

-160

-180 Label Asm. Label Type 2

Lll Format 3

L12 Format 4

L13 Format 6

L14 Executable 7

L15 Format 9

L17 Format 15 L18 Format 20 L16 Executable 100 L19 Executable 105 L20 Format Line Number(s) 57*

73*

78*

82*

83*

92*

110*

112*

117*

121*

56 72 77 115 82 86 91 109 89 82 120

A AREVA Evaluation of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A Messier Framatome ANP, Inc., an AREVA and Siemens company Tue Oct 19 08:44:58 2004 pnpswd.f Document ID 32-5052036-00 Page 25 HP FORTRAN 77 Ver: B.20.20 Page 5

Final Compilation Statistics for file: pnpswd.f Accumulated errors:

0 Number of Warnings:

Total number of procedures:

1 Accumulated number of source lines read:

125 0

Timing Statistics for:

f77passl:

real:

0.16s user:

O.OOs sys:

0. oos

A ARE VA Evaluation of Pilgnn Nudear Power Station 1996-2001 Meteorological Data Prepared by. Theodore A. Messier Finmatomc ANP, Inc., an AREZVA andSiemens company Document ID 3Z-5052036-00 Page 26 ATTACHMENT D: COMPUTER CODE BECHECK LISTING PROGRAM BECHECK C THIS PROGRAM READS BECO METEOROLOGICAL DATA IN THEIR FORMAT AND CHECKS C FOR SUSPECT DATA.

C THE PROGRAM PROMPTS THE USER FOR THE NAME OF THE INPUT FILE.

C THE PROGRAM OUTPUTS FILES CONTAINING SUSPECT DATA DATES AND TIMES FOR C THE USER TO THEN USE AS A GUIDE.

C THE PROGRAM WAS DESIGNED TO BE USED ON UP TO ONE YEAR OF MET. DATA.

C C CORRECTED MINOR BUG IN LL WS STUCK SENSOR CHECK; WAS PRINTING C BACKUP LL WS INSTEAD OF PRIMARY LL WS ON PRIMARY CHECK C

C C

(NIGHT - HOURS 20 -

3; DAY HOURS 8 -

16)

CHARACTER*12 INFILE,OUTFILI,OUTFIL2,OUTFIL3,OUTFIL4 CHARACTER*12 OUTFIL5,OUTFIL6,OUTFIL7,OUTFIL8,outfil9 INTEGER YEAR(9000),MONTH(9000),DAY(9000),HOUR(9000),J REAL WD160(9000),WS160(9000),WD33B(9000),WS33B(9000),T33B(9000)

REAL DELTATB(9000)

REAL WD220(9000),WS220(9000),WD33P(9000),WS33P(9000),T33P(9000)

REAL DELTATP(9000)

C ASK USER FOR THE INPUT FILE NAME WRITE (*,*)

ENTER THE NAME READ (*,1) INFILE 1

FORMAT(A12)

OF THE INPUT FILE (IN BECO FORMAT)'

C NAME THE OUTPUT FILES OUTFIL1'=BECHECK.DTB' OUTFIL2='BECHECK.DTP' OUTFIL3='BECHECK.TB' OUTFIL4='BECHECK.TP' OUTFIL5='BECHECK.SB' OUTFIL6='BECHECK.SP' OUTFIL7-'BECHECK.WD' C

OUTFIL7-'BECHECK.DB' C

OUTFIL8='BECHECK.DP' OUTFIL9='BECHECK.dr' C OPEN THE INPUT FILE OPEN(15,FILE-INFILE)

C OPEN THE OUTPUT FILES OPEN(16,FILE-OUTFILl)

-WRITE(16,2) 2 FORMAT('

BECO OPEN(17,FILE=OUTFIL2)

WRITE(17,3) 3 FORMAT('

BECO OPEN(18,FILE=OUTFIL3)

WRITE(18,4) 4 FORMAT('

BECO OPEN(19,FILE=OUTFIL4)

BACKUP TOWER SUSPECT DELTA-T DATA')

PRIMARY TOWER SUSPECT DELTA-T DATA')

BACKUP TOWER SUSPECT TEMP. DATA')

A AR EVA Evaluation of Pilgrm Nuclear Power Staton 1996-2001 Meteorological Data Prepared by: Theodore A Messier Frarnatome ANP. Inc.. anAREVA and Siemens companv Document ID 32-5052036-00 Page 27 WRITE (19,5) 5 FORMAT('

BECO PRIMARY TOWER SUSPECT TEMP.

DATA')

OPEN(20, FILE=OUTFIL5)

WRITE (20,6) 6 FORMAT ('

BECO BACKUP TOWER SUSPECT WIND SPEED DATA')

OPEN (21, FILE=OUTFIL6)

WRITE (21,7) 7 FORMAT('

BECO PRIMARY TOWER SUSPECT WIND SPEED DATA')

OPEN(22, FILE=OUTE'IL7)

WRITE (22,8) 8 FORMAT('

BECO SUSPECT WIND DIRECTION DATA')

C OPEN (22, FILE=OUTFIL7)

C WRITE(22,8)

C8 FORMAT('

BECO BACKUP TOWER SUSPECT WIND DIRECTION DATA')

C OPEN (23, FILE-OUTFIL8)

C WRITE (23,9)

C9 FORMAT('

BECO PRIMARY TOWER SUSPECT WIND DIRECTION DATA')

OPEN (24, FILE=OUTFIL9)

WRITE(24,10) 10 FORMAT ('

BECO DATA RECOVERY RATES')

C WRITE OUTPUT FILE TITLE C

WRITE(16,*)

C WRITE(16,12)

EXT,YR C12 FORMAT(24X,'BECO METEOROLOGICAL DATA FOR ',A3,',

19',A2)

C WRITE(16,*)

C WRITE(16,*)'

BACKUP TOWER C

PRIMARY TOWER '

C WRITE DATA HEADERS -

DESCRIPTIVE TEXT C

WRITE (16,13)

C13 FORMAT('YR MN DY HR WD160 WS160 WD33 WS33 T33 DELTL C

0 WD33 WS33 T33 DELTU')

C WRITE(16,*)

WD220 WS22 C

ZERO OUT DATA ARRAYS DO 14 1=1,9000 YEAR(I)-O MONTH (I) =0 DAY(I)=O HOUR(I)hO WD160 (I) =0. 0 WS160 (I)=0.0 WD33B(I)=0.0 WS33B(I)=0.0 T33B (I) 0.0 DELTATB(I)=O.0 WD220(I)=0.0 WS220(I)=0.0 WD33P(I)=0.0 WS33P(I)=0.0 T33P(I)=0.0 DELTATP(I)=0.0 14 CONTINUE inumup-0 inumdn=0

A Evaluation of Pilgrm Nuclear Power Staton Document ID 32-5052036-00 A

1996-2001 Meteorological Data A R EVA Prepared by: Theodore A. Messier Page 28 Framatome ANP, Inc., an AREVA andSiemens company C READ THE METEOROLOGICAL DATA; WHEN REACH END OF FILE, GOTO 30 J=1 15 READ(15,20,END=30) YEAR(J),MONTH(J),DAY(J),HOUR(J),WD160(J),

&WS160(J),WD33B(J),WS33B(J),T33B(J),DELTATB(J),WD220(J),WS220(J),

&WD33P(J),WS33P(J),T33P(J),DELTATP(J) 20 FORMAT(4(I2,lX),T15,F5.0,T20,F5.1,T25,F5.0,T30,F5.1,T35,F5.0,T40,F

&5.1,T50,F5.0,T55,F5.1,T60,F5.O,T65,F5.1,T70,F5.0,T75,F5.1)

IF((WD220(j).lt.999.).and.(WS220(j).lt.99.9).and.(deltatp(j).lt.

&99.9)) inumup-inumup+l IF((WD33P(j).lt.999.).and.(WS33P(j).lt.99.9).and.(deltatp(j).lt.

&99.9)) inumdn-inumdn+l J=J+1 GOTO 15 30 CONTINUE C ILASTHR IS LAST HOUR HAVING DATA BEFORE EOF WAS ENCOUNTERED ILASTHR=J-1 ptdn-float(inurdn)/float(ilasthr)*100.

ptup=float(inumup)/float(ilasthr)*100.

write(24,*) "

write(24,*)' BECo meteorological data recovery for the period' write(24,22)month(l),day(l),year(1),nonth(ilasthr),day(ilasthr),

&year(ilasthr) 22 format(l5x,i2,'/',i2,'/',i2,' to ',i2,'/',i2,'/',i2,'.')

write (24, *) II write(24,23)ptdn 23 format(' Primary tower lower level composite data recovery is:

& ',f6.2,'%')

write(24,*)'"

write(24,24)ptup 24 format(' Primary tower upper level composite data recovery is:

& ',f6.2,'%')

write(24,*)

write(24,*)' (Note that the composite recovery reported is the per

&cent of time' write(24,*)' that wind speed, wind direction, and delta temperatur

&e were I write(24,*)' available simultaneously.)'

C LOOK FOR SUSPECT DELTA-T VALUES DO 40 I-1,ILASTHR IF((DELTATB(I).GT.90.).OR.(DELTATP(I).GT.90.))GOTO 40 C LOOK FOR UNSTABLE CONDITIONS AT NIGHT (HOURS 20 -

3)

IF((HOUR(I).GE.20).OR.(HOUR(I).LE.3))THEN IF(DELTATB(I).LE.-l.l)WRITE(16,31)YEAR(I),MONTH(I),DAY(I),HOUR (I),DELTATB(I)

IF(DELTATP(I).LE.-l.6)WRITE(17,31)YEAR(I),MONTH(I),DAY(I),HOUR (I),DELTATP(I) 31 FORMAT(/,4(I2,1X),F5.l,' UNSTABLE VALUE AT NIGHT ')

C LOOK FOR VERY UNSTABLE CONDITIONS DURING THE DAY (HOURS 8 -

16)

ELSEIF((HOUR(I).GE.8).AND.(HOUR(I).LE.16))THEN IF(DELTATB(I).LE.-2.0)WRITE(16,32)YEAR(I),MONTH(I),DAY(I),HOUR

0 A

AR EVA Evaluaton of Pilgrn Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Frarnatome ANP. Inc.. an AREVA and Siemens company Document ID 32-5052036-0 Page 29 (I),DELTATB(I)

IF(DELTATP(I).LE.-3.O)WRITE(17,32)YEAR(I),MONTH(I),DAY(I),HOUR (I),DELTATP(I) 32 FORMAT(/,4(I2,1X),F5.1,' VERY UNSTABLE VALUE ')

ELSE ENDIF 40 CONTINUE C LOOK FOR DAYS THAT HAVE STABLE CONDITIONS EVERY HOUR IB=o IP-0 DO 50 I=24,ILASTHR,24 IF(DELTATB(I).GT.90.)GOTO 45 IF(DELTATB(I).GE.-0.34)IB-IB+1 IF(DELTATB(I-1).GE.-0.34)IB=IB+l IF(DELTATB(I-2).GE.-O.34)IB-IB+1 IF(DELTATB(I-3).GE.-0.34)IB-IB+1 IF(DELTATB(I-4).GE.-O.34)IB=IB+1 IF(DELTATB(I-5).GE.-O.34)IB-IB+1 IF(DELTATB(I-6).GE.-O.34)IB-IB+1 IF(DELTATB(I-7).GE.-0.34)IB=IB+1 IF(DELTATB(I-8).GE.-0.34)IB-IB+1 IF(DELTATB(I-9).GE.-O.34)IB=IB+1 IF(DELTATB(I-10).GE.-0.34)IB=IB+1 IF(DELTATB(I-11).GE.-O.34)IB-IB+l IF(DELTATB(I-12).GE.-0.34)IB=IB+1 IF(DELTATB(I-13).GE.-O.34)IB=IB+1 IF(DELTATB(I-14).GE.-0.34)IB-IB+1 IF(DELTATB(I-15).GE.-0.34)IB=IB+1 IF(DELTATB(I-16).GE.-O.34)IB-IB+1 IF(DELTATB(I-17).GE.-0.34)IB-IB+1 IF(DELTATB(I-18).GE.-O.34)IB=IB+1 IF(DELTATB(I-19).GE.-O.34)IB-IB+l IF(DELTATB(I-20).GE.-O.34)IB=IB+1 IF(DELTATB(I-21).GE.-O.34)IB=IB+1 IF(DELTATB(I-22).GE.-O.34)IB-IB+1 IF(DELTATB(I-23).GE.-O.34)IB=IB+1 IF(IB.EQ.24)THEN WRITE(16,42)YEAR(I),MONTH(I),DAY(I) 42 FORMAT(/,lX,3(12,1X),' STABLE ALL DAY ')

ELSE IB=O ENDIF 45 IF(DELTATP(I).GT.90.)GOTO 50 IF(DELTATP(I).GE.-0.5)IP=IP+1 IF(DELTATP(I-1).GE.-0.5)IP=IP+l IF(DELTATP(I-2).GE.-0.5)IP-IP+1 IF(DELTATP(I-3).GE.-0.5)IP=IP+1 IF(DELTATP(I-4).GE.-0.5)IP-IP+1 IF(DELTATP(I-5).GE.-0.5)IP=IP+1 IF(DELTATP(I-6).GE.-0.5)IP=IP+1 IF(DELTATP(I-7).GE.-0.5)IP-IP+1 IF(DELTATP(I-8).GE.-0.5)IP=IP+1 IF(DELTATP(I-9).GE.-0.5)IP-IP+1 IF(DELTATP(I-10).GE.-O.5)IP=IP+1

A Evaluaton of Pilgrm Nuclear Power Staton Document ID 32-5052036-00 A

1996-2001 Meteorological Data A R E VA Prepared by. Theodore A. Messier Page 30 Framatome ANP. Inc., anAREVA andSiemens company IF(DELTATP(I-il).GE.-0.5)IP=IP+I IF(DELTATP(I-12).GE.-O.5)IP-IP+1 IF(DELTATP(I-13).GE.-O.5)IP=IP+1 IF(DELTATP(I-14).GE.-0.5)IP=IP+1 IF(DELTATP(I-15).GE.-O.5)IP-IP+1 IF(DELTATP(I-16).GE.-0.5)IP=IP+1 IF(DELTATP(I-17).GE.-0.5)IP=IP+1 IF(DELTATP(I-18).GE.-0.5)IP-IP+1 IF(DELTATP(I-19).GE.-O.5)IP=IP+1 IF(DELTATP(I-20).GE.-O.5)IP-IP+1 IF(DELTATP(I-21).GE.-O.5)IP-IP+1 IF(DELTATP(I-22).GE.-O.5)IP=IP+1 IF(DELTATP(I-23).GE.-O.5)IP=IP+I IF(IP.EQ.24)THEN WRITE(17,42)YEAR(I),MONTH(I),DAY(I)

ELSE IP=0 ENDIF 50 CONTINUE C LOOK FOR SUSPECT TEMPERATURE DATA (I HR CHANGE OF > 10 DEG F)

IEND=ILASTHR-1 DO 60 I=1,IEND IF((T33BCI).GT.99.).OR.(T33B(I+l).GT.99.))GOTO 53 C

BACKUP TOWER LOWER LEVEL TEMPERATURE TTB1=T33B(I)+10.0 TTB2-T33B(I)-10.0 IF((T33B(I+l).GE.TTBl).OR.(T33B(I+l).LE.TTB2))THEN WRITE(18,52)YEAR(I+l),MONTH(I+1),DAY(I+l),HOUR(I+1),T33B(I+l) 52 FORMAT(/,1X,4(I2,1X),F5.0,' TEMP. CHANGE > 10 DEG F !!!!!')

ELSE ENDIF 53 IF((T33P(I).GT.99.).OR.(T33PCI+1).GT.99.))GOTO 60 C PRIMARY TOWER LOWER LEVEL TEMPERATURE TTP1T33P(I)+10.0 TTP2=T33P(I)-10.0 IF((T33P(I+1).GE.TTPl).OR.(T33P(I+1).LE.TTP2))THEN WRITE(19,52)YEAR(I+1),MONTH(I+1),DAY(I+1),HOUR(I+l),T33P(I+l)

ELSE ENDIF 60 CONTINUE C CHECK FOR SUSPECT WIND SPEED DATA - LOOK FOR STUCK WS SENSOR:

C IF WS IS SAME FOR A FOUR HOUR PERIOD, ASSUME SENSOR IS STUCK DO 70 I=4,ILASTHR,4 IF(WS33B(I).GT.999.)GOTO 64 IF((WS33B(I).EQ.WS33B(I-1)).AND.(WS33B(I).EQ.WS33B(I-2)).AND.(WS

& 33B(I).EQ.WS33B(I-3)))THEN WRITE(20,65)YEAR(I),MONTH(I),DAY(I),HOUR(I),WS33B(I) 65 FORMAT(/,1X,4(I2,1X),F5.1,' LL WS SENSOR MAY BE STUCK')

ELSE ENDIF 64 IF(WS160(I).GT.999.)GOTO 63 I F ((WS1 60 (I).EQ. WS 16 0(I-1)).AND. (WS1 60 (I).EQ.WS 160 (I-2)).AND

&.(WS160(I).EQ.WS160(I-3)))THEN WRITE(20,66)YEAR(I),MONTH(I),DAY(I),HOUR(I),WS160(I) 66 FORMAT(/,1X,4(I2,1X),F5.1,' UL WS SENSOR MAY BE STUCK')

A Evaluation of Pilgrrn Nuclear Power Stabon Document ID 32-5052036-00 A1996-2001 Meteorological Data A R E VA Prepared by: Theodore A. Messier Page 31 Franmatome ANP, Inc, an AREVA and Siemens company ELSE ENDIF 63 IF(WS33P(I).GT.999.)GOTO 62 IF((WS33P(I).EQ.WS33P(I-1)).AND.(WS33P(I).EQ.WS33P(I-2)).AND.(WS

& 33P(I).EQ.WS33P(I-3)))THEN WRITE(21,65)YEAR(I),MONTH(I),DAY(I),HOUR(I),WS33P(I)

ELSE ENDIF 62 IF(WS220(I).GT.999.)GOTO 70 IF((WS220(I).EQ.WS220(I-1)).AND.(WS220(I).EQ.WS220(1-2)).AND

&.(WS220(I).EQ.WS220(I-3)))THEN WRITE(21,66)YEAR(I),MONTH(I),DAY(I),HOUR(I),WS220(I)

ELSE ENDIF 70 CONTINUE C

C CHECK FOR SUSPECT WIND DIRECTION DATA -

COMPARE THE TWO TOWERS; IF WITHIN C 22 DEG OF ONE ANOTHER ASSUME THEY ARE OKAY; OTHERWISE, ASSUME THERE IS A C PROBLEM WITH ONE OF THE TOWERS C IF ONE WD VALUE IS BETWEEN 270 AND 360 AND THE OTHER IS BETWEEN 0 AND 90, C THEN ADD 360 TO THE VALUE BETWEEN 0 AND 90 BEFORE TESTING.

C IUWD=0 DO 80 I-1,ILASTHR IF((WD220(I).GT.900.).OR.(WD160(I).GT.900.))GOTO 80 IF((WD220(I).GE.270.).AND.(WD220(I).LE.360.).AND.(WD160(I).GE.

& 0.0).AND.(WD160(I).LE.90))WD160(I)-WD160(I)+360.

IF((WD160(I).GE.270.).AND.(WD160(I).LE.360.).AND.(WD220(I).GE.

& 0.0).AND.(WD220(I).LE.90))WD220(I)-WD220(I)+360.

PUP=WD220(I)+22.

PUM=WD220(I)-22.

IF((WD160(I).GE.PUM).AND.(WD160(I).LE.PUP))THEN IUWD=IUWD+1 ELSE WRITE(22,75)YEAR(I),MONTH(I),DAY(I),HOUR(I) 75 FORMAT(/,lX,4(I2,1X),'

UL WD VALUES > 22 DEG APART UL WD')

ENDIF 80 CONTINUE ILWD=0 DO 90 I-1,ILASTHR IF((WD33P(I).GT.900.).OR.(WD33B(I).GT.900.))GOTO 90 IF((WD33P(I).GE.270.).AND.(WD33P(I).LE.360.).AND.(WD33B(I).GE.

& 0.0).AND.(WD33B(I).LE.90))WD33B(I)-WD33B(I)+360.

IF((WD33B(I).GE.270.).AND.(WD33B(I).LE.360.).AND.(WD33P(I).GE.

& 0.0).AND.(WD33P(I).LE.90))WD33P(I)-WD33P(I)+360.

PLP=WD33P(I)+22.

PLM=WD33P(I)-22.

IF((WD33B(I).GE.PLM).AND.(WD33B(I).LE.PLP))THEN ILWD=ILWD+1 ELSE WRITE(22,85)YEAR(I),MONTH(I),DAY(I),HOUR(I) 85 FORMAT(/,1X,4(I2,1X),'

LL WD VALUES > 22 DEG APART LL WD')

ENDIF 90 CONTINUE 100 CLOSE(15)

A AR EVA Evaluation of Pilgmn Nuclear Power Station 1996-2001 Meteorological Data Prepared by: Theodore A. Messier Franiatome ANP, Inc., anAREVA and Siemens company Document ID 32-5052036-00 Page 32 CLOSE (16)

CLOSE (17)

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STOP END

20032-33 (6/2312004)

A RELEASE DATE A

DOCUMENT RELEASE NOTICE REESEDT AR EVA RM INITIALS CONTRACT NUMBER PLANT CC OR CHARGE NUMBER 4170698 Pilgrim Nuclear Power Station 4170698 PAGE 1 OF 1 PART OR TASK No.

DOCUMENT DOCUMENT TITLE CLASS PUL COLD COM (N/A If Not Applicable)

NUMBER (SINS)

(YIN)

(Y/N)

Conversion of Pilgrim Nuclear Power Station N/A 32-5052125-00 1996-2001 Meteorological Data for Use With S

N Y

N ARCON96 KEYWIORDS (For Informational Purposes Only)

SPECIAL REQUESTS LABEL COPIES Meteorology, ARCON96 El CD OF COWD 0

El OTHER (Specify Below I.e. Reproduction Instructions)

INFORMATIONAL DISTRIBUTION (Electronic Notification Only)

REQUIRED DISTRIBUTION'*

MAIL CODE COPIES Richard J. Cacciapouti TOTAL NUMBER OF HARDCOPIES KEYWORDS(STAPLED IS DEFAULT UNLESS SPECIAL REQUEST) 0 RELEASED BY (PRINT NAME)

REVIEWED BY (PRINT NAME)

PM FUNCTIONAL APPROVAL (IF APPLICABLE)

Theodore A. Messier Richard J. Cacciapouti SIGNATURE DAT USIGNATURE DA T REGULATORYAFFAIRS(IF APPLICABLE)

TECHNICAL MANAGER(IFAPPLC E

IFF

.<2,N/ANA 4Ted Messier N/ANA SIG URE DOT MAIL CODE

+sSGAUEDATE SIGNATURE DAEte2378 37&23

~ SIGATURED

-T

__ATEAsI_

- :ee URN instructions tor signature requirements.

Framatome ANP, Inc., an AREVA and Siemens company Refer to Procedure 0412-66

20697-8 (4/1/2004)

At CALCULATION

SUMMARY

SHEET (CSS)

AREVA Document Identifier 32-5052125-00 Title Conversion of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96 PREPARED BY:

REVIEWED BY:

METHOD:

3 DETAILED CHECK El INDEPENDENT CALCULATION NAME Theodore A. Messier NAME John N. Hamawi SIGNATURE 3D4,'d&1 a..

SIGNATURE

^

/'

3 c

?

TITLE Meteorologist DATE i6ans4 TITLE nsulting Radiological Eng.

DATE COST REF.

IM STATEMENT:

CENTER 41758 PAGE(S) 7 REVIEWER INDEPENDENCE PURPOSE AND

SUMMARY

OF RESULTS:

Purpose Convert meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2001 into a format suitable for use with computer code ARCON96.

Results Meteorological data recorded on the 220' primary tower by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2001 were converted into a format suitable for use with computer code ARCON96.

This calculation is safety related and was prepared under the AREVANFramatome ANP Quality Assurance Program.

THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFETY-RELATED WORK CODE/VERSION/REV CODE/VERSION/REV YES 3

NO Framatome ANP, Inc., an AREVA and Siemens company Page I

of 16

22410-3 (5/10/2004) 1 of2 At DESIGN VERIFICATION CHECKLIST ARE VA Document Identifier 32-5052125-00 Page 2 of 16 Conversion of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data for Use With Title ARCON96

1.

Were the inputs correctly selected and incorporated into design or analysis?

Y El N El N/A

2.

Are assumptions necessary to perform the design or analysis activity adequately El Y E

N

] N/A described and reasonable? Where necessary, are the assumptions identified for lsubsequent re-verifications when the detailed design activities are completed?

3.

Are the appropriate quality and quality assurance requirements specified? Or, for I Y El N a

N/A documents prepared per FANP procedures, have the procedural requirements been m et?_

4.

If the design or analysis cites or is required to cite requirements or criteria based upon Y

E N

applicable codes, standards, specific regulatory requirements, including issue and addenda, are these properly identified, and are the requirements/criteria for, design or i

analysis met?'

5.

Have applicable construction and operating experience been considered?

al Y NN/A

6.

Have the design interface requirements been satisfied?

D Y D_ N i

N/A

7.

Was an appropriate design or analytical method used?

_Y _

N

_N/A

8.

Is the output reasonable compared to inputs?

l Y El N E

N/A

9.

Are the specified parts, equipment and processes suitable for the required application?

El Y E

N

___N/A

10.

Are the specified materials compatible with each other and the design environmental E

Y Cl N Z

N/A conditions to which the material will be exposed?

11.

Have adequate maintenance features and requirements been specified?

E Y

E N

N/A

12.

Are accessibility and other design provisions adequate for performance of needed E

Y E

N N/A maintenance and repair?

13.

Has adequate accessibility been provided to perform the in-service inspection expected El Y El N 1IN/A to be required during the plant life?

14.

Has the design properly considered radiation exposure to the public and plant El Y El N 0N/A personnel?

15.

Are the acceptance criteria incorporated in the design documents sufficient to allow E

Y E N

[5'N/A verification that design requirements have been satisfactorily accomplished?

16.

Have adequate pre-operational and subsequent periodic test requirements been El Y El N Era N/A appropriately specified?

17.

Are adequate handling, storage, cleaning and shipping requirements specified?

C Y

a N

@!N/A

18.

_Ar adequate identification requirements specified?

ElY N

[giN/A

19.

Is the document prepared and being released under the FANP Quality Assurance e

Y N

El N/A Program? If not, are requirements for record preparation review, approval, retention, etc., adequately specified?

Framatome ANP, Inc., an AREVA andSiemens company

22410-3 (5/10/2004) 2 of2 AR EVADESIGN VERIFICATION CHECKLIST I Document Identifier:

32-5052125-00 Paze 3 of 16 Comments:

Verified By:

John N. Hamawi (First, MI, Last)

Printed a Typed Name ignature Date Framiatomne ANP, Inc., an ARE VA and Siemens conpany

A AR EVA Conversion of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96 Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052125-00 Page 4 RECORD OF REVISIONS Place holder for future revisions, if any.

A Conversion of Pilgrm Nuclear Power Station Document ID 32-5052125-00 A1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A. Messier Page 5 Framatome ANP, Inc., an AREVA and Siemens company TABLE OF CONTENTS CALCULATION

SUMMARY

SHEET (CSS) 1 DESIGN VERIFICATION CHECKLIST................................

2 RECORD OF REVISIONS....................................

4 TABLE OF CONTENTS....................................

5 1.0 PurposeObjective

.6 2.0 Assumptions and Key Assumptions

.6 3.0 Computing Environment

.6 4.0 Quality Assurance

.6 5.0 Calculations.............................................................................................................................6 6.0 ResultslConclusion

.7 7.0 References

.7 Exhibit 1: Input Meteorological Data Format....................................

8 ATTACHMENT A: COMPUTER CODE REFORM LISTING........

9 ATTACHMENT B: COMPUTER INPUT AND OUTPUT FILES.................................... 15 ATTACHMENT C: Validation of Computer Code reform....................................................................... 16

A Conversion of Pilgrm Nuclear Power Station Document ID 32-5052125-00 1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A Messier Page 6 Franmatome ANP. Inc., an AREVA and Siemens company 1.0 PurposelObjective Convert meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station (PNPS) from January 1996 through December 2001 into a format suitable for use with computer code ARCON96 as requested in EntergylPilgrim Contract Order Number 4500534887 (Reference 1).

2.0 Assumptions and Key Assumptions Since the base of the backup meteorological tower is not located on a natural surface, it was assumed that the data from that tower were not suitable for use in this calculation.

A key assumption is any assumption or limitation that must be verified prior to using the results and/or conclusions of a calculation for a safety-related task. There are no key assumptions in the present calculation.

3.0 Computing Environment The computer runs in this calculation involved the use of computer code reform and were carried out on the HP 9000/785 CPU running the HP UX B.10.20 operating system. Computer code reform was written expressly for use in this calculation and its usage is validated in Attachment A.

4.0 Quality Assurance This work was performed under Framatome's Quality Assurance Program, and Framatome Procedure 0402-01 (Preparing and Processing FANP Calculations) was followed.

5.0 Calculations Meteorological data recorded by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2001 were evaluated in Reference 2 and determined to be suitable for use in atmospheric dispersion analyses. The temperature sensor separation was obtained from Reference 4.

Computer code reform was developed specifically for this calculation to reformat the 1996.2001 PNPS meteorological data from its standard format to the format required by the ARCON96 computer code. A listing of this code is provided in Attachment A. The source code file name is reformmf and the executable file name is reform.e. The file sizes in bytes and the creation dateltime are:

permissions file owner group size in bytes date/time file name

-rwxrwxrwx 1 messier eed 41060 Oct 19 09:34 reforme

-rw-r-----

1 messier eed 5398 Oct 19 09:34 reform.f Each of the six annual meteorological files were input to reform and two files were output in each of the six runs: the so-called banner file which lists the computer code name, version number, inpuVoutput file names, and run date; the main output file of meteorological data converted for use with compute code ARCON96.

The input meteorological data (see Exhibit I for format), the reformatted meteorological data (see Reference 3 for format), and the source code for the reform computer code have been stored on the FANP COLD server for archival storage and written to a compact disc for PNPS. A listing of the file names is provided in Attachment B.

A Conversion of Pilgrn Nuclear Power Station Document ID 32-5052125-00 1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A. Messier Page 7 Frarnatome ANP, Inc., an AREVA and Siemens company Testing and validation of the reform computer code is documented in Attachment C. The reform computer code was run on an HP UNIX Workstation 90001785 under the HP-UX UNIX B.1 0.20 operating system.

6.0 ResultslConclusion Meteorological data recorded on the 220' primary tower by the onsite meteorological monitoring system at Pilgrim Nuclear Power Station from January 1996 through December 2001 were converted into a format suitable for use with computer code ARCON96.

7.0 References

1. Entergy/Pilgrim Contract Order Number 4500534887.

2. FANP Calculation 32-5052036-00, 'Evaluation of Pilgrim Nuclear Power Station 1996-2001 Meteorological Data", dated October 2004.

3.- U.S. Nuclear Regulatory Commission Regulatory Guide 1.194, 'Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants", June 2003.

4. AREVAIFANP Calculation BEC-018, Revision 1, 'Meteorological Inputs to the AEOLUS-2 Program for Pilgrim Station", dated 10123191.

Conversion of Pilgrm Nuclear Power Station Document ID 32-5052125-00 1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A Messier Page 8 Framatome ANP, Inc., an AREVA and Siemens company Exhibit 1: Input Meteorological Data Format Parameter (units)

J of Chars. Columns Year 2

01-02 Month 2

04-05 Day 2

07-08 Hour 2

10-11 160 Foot Tower: (See note below.)

Wind Direction; 160 ft (degrees from) 4 15-18 Wind Speed; 160 ft (tenths of mph) 4 20-23 Wind Direction; 33 ft (degrees from) 4 25-28 Wind Speed; 33 ft (tenths of mph) 4 30-33 Temperature; 33 ft (degrees F).

4 35-38 Delta T; 160-33 ft (Tenths of degrees F) 4 40-43 220 Foot Tower:

Wind Direction; 220 ft (degrees from) 4 50-53 Wind Speed; 220 ft (tenths of mph) 4 55-58 Wind Direction; 33 ft (degrees from) 4 60-63 Wind Speed; 33 ft (tenths of mph) 4 65-68 Temperature; 33 ft (degrees F) 4 70-73 Delta T; 220-33 ft (Tenths of degrees F) 4 75-78 Note: Data from the 160' tower are not in the data files to insure that they are not used. The rest of the data files input to reform were in the format listed above.

A AR EVA Conversion of Pilgrrn Nuclear Power Staton 1996-2001 Meteorological Data for Use With ARCON96 Prepared by: Theodore A Messier Framatome ANP. Inc., an AREVA and Siemens company Document ID 32-5052125-00 Page 9 ATTACHMENT A: COMPUTER CODE REFORM LISTING HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 09:34:45 2004 reform. f Page 1

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15

.16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 C

C C

C C.

C Program reform Version 1.0 This program reformats PNPS standard meteorological data to the format required by ARC0N96.

It asks the user for the input (in old BECo format) and output file names, one at a time.

For each year processed, it asks whether it is a leap year, for use in the date conversion to julian.

The program assumes that the wind direction values are between 0 and 360 degrees, that the wind speed units are MPH, and that the delta-T units are degrees Fahrenheit.

FANP Written on 10-05-2004 by T;A. Messier c**********

character infile*60,outfile*60,leap,ident*5,banner*20 character*9 today real uws,uwd,lws,lwd,temp,delt c**********

ident='PNPS banner-'reform banner.txt' C

c**** Loop through all years of interest 50 write(*,*) ' Enter the met data input file name for ',

m

'the year of interest,'

write(*,*) ' or enter "stop" to end:

read(*,*) infile if(infile.eq.'stop') go to 400 open(15,file-infile,status-'old',err-50) outfile='pnps'//infile(6:7)//'.met' banner-'reform banner.'//infile(6:7) open(16,file-outfile,status-'new')

60 C

82 open(26,file=banner) write (26, 60) format(/,' FANP Program reform version 1.0 ',/,l)

Get the run date call date(today) 80 write(*,*) ' Is the selected year a leap year? (Enter y or n):'

read(*,*) leap if(leap.ne.'y'.and.leap.ne.'n') go to 80 I

Write run info to banner file write(26,82)infile,outfile,today,leap format('

Input file name : ',a60,/,'

&60,/,/,'

Run Date

',a9,/,/,I

&al,/,/)

Output file name:

',a Leap Year

Conversion of Pilgrm Nuclear Power Station Document ID 32-5052125-00 A1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A. Messier Page 10 Framnaome ANP, Inc., an AREVA and Siemens company HP FORTRAN 77 Tue Oct 19 09:34:45 2004 Ver: B.10.20 reform.f Page 2

54 55 c**

Read the met data file 56 iseq - 0 57 100 iseq -iseq + 1 58 read(15,2000,end-300) iyear,imonth,iday,ihour,uwd,uws,lwd,lws, 59 m temp,delt 60 if~iday.eq.0) then 61 iseq - iseq - 1 62 go to 100 63 endif 64 c 65 c**

Figure out from month and day of year what julian date it is 66 c 67 if(imonth.eq.1) juldate - iday 68 if(imonth.eq.2) juldate - iday + 31 69 if(leap.eq.'y') then 70 if(imonth.eq.3) juldate - iday + 60 71 if(imonth.eq.4) juldate -

iday + 91 72 if(imonth.eq.5) juldate -

iday + 121 73 ifCimonth.eq.6) juldate -

iday + 152 74 if(imonth.eq.7) juldate - iday + 182 75 if(imonth.eq.8) juldate -

iday + 213 76 if(imonth.eq.9) juldate - iday + 244 77 if(imonth.eq.10) juldate -

iday + 274 78 if(imonth.eq.11) juldate - iday + 305 79 if(imonth.eq.12) juldate -

iday + 335 80 else 81 if(imonth.eq.3) juldate -

iday + 59 82 if(imonth.eq.4) juldate -

iday + 90 83 if(imonth.eq.5) juldate -

iday + 120 84 if(imonth.eq.6) juldate -

iday + 151 85 if(imonth.eq.7) juldate -

iday + 181 86 if(imonth.eq.8) juldate -

iday + 212 87 if(imonth.eq.9) juldate -

iday + 243 88 if(imonth.eq.10) juldate -

iday + 273 89 if(imonth.eq.11) juldate - iday + 304 90 if(imonth.eq.12) juldate -

iday + 334 91 endif 92 c**

Check for missing hourly data 93 julday2 = (iseq-l)/24 + 1 94 if(juldate.ne.julday2) then 95 write(*,*)

96 write(*,*) ' Missing hourly data encountered.

Check:'

97 write(*,*) iyear,iday,imonth,ihour 98 write(*,*) ' Analysis terminated!'

99 stop 100 endif 101 c

102 c**

Process wind speed and wind directions for ARCON96 103 c 104 c Lower-level and upper-level wind speeds 105 if(lws.lt.99.0) then 106 ilws -

nint(lws*10.) + 0.01

Conversion of Pilgrm Nudear Power Staton Document ID 32-5052125-00 A1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A. Messier Page 11 Franatome ANP, Inc.. an AREVA and Siemens company HP FORTRAN 77 Tue Oct 19 09:34:45 2004 Ver: B.10.20 reform.f Page 3

107 else 108 ilws = 9999 109 endif 110 c

111 if(uws.lt.99.0) then 112 iuws - nint(uws*l0.) + 0.01 113 else 114 iuws -

9999 115 endif 116 c 117 c Lower-level and upper-level wind directions 118 if(uwd.le.360.0) then 119 iuwd = nint~uwd) + 0.01 120 iuwd = mod(iuwd,360) 121 if(iuwd.lt.1) iuwd - 360 122 else 123 iuwd -

999 124 endif 125 c 126 if(lwd.le.360.0) then 127 ilwd - nint(lwd) + 0.01 128 ilwd -

mod(ilwd,360) 129 if(ilwd.lt.1) ilwd -

360 130 else 131 ilwd -

999 132 endif 133 c 134 c**

Process delta-T and identify stability class, based on RG 1.23 135 c Use delt for ground-level releases, and delt for stack releases 136 c since there is only one delta-T observation for PNPS 220' tower 137 dt -

delt 138 dh = (220.0 -

33.0)*0.3048 139 if (dt.gt.99.)then 140 c data is either bad, or missing 141 istab -

99 142 goto 200 143 else 144 dt -

dt*(5.0/9.0)*(100.0/dh) 145 if(dt.le.-l.9) then 146 istab -

1 147 elseif((dt.gt.-l.9).and.(dt.le.-1.7)) then 148 istab = 2 149 elseif((dt.gt.-1.7).and.(dt.le.-l.5)) then 150 istab -

3 151 elseif(Cdt.gt.-l.5).and.(dt.le.-O.5)) then 152 istab - 4 153 elseif(Cdt.gt.-0.5).and.(dt.le.1.5)) then 154 istab - 5 155 elseif((dt.gt.1.5).and.(dt.le.4.0)) then 156 istab -

6 157 elseif(dt.gt.4.0) then 158 istab = 7 159 else

A AR EVA Conversion of Pilgrm Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96 Prepared by-Theodore A. Messier Framatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052125-00 Page 12 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 09:34:45 2004 reform.f Page 4

160 161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 endif endif 200 write(16,2100) identiyear,juldate,ihour,ilwd,ilws,istab,iuwdiuws go to 100 300 continue close (15) close (26) go to 50 400 close (16) stop 'PNPS meteorological data reformated for ARCON96' c

c**********

2000 format(4(i2,lx),t50,f4.0,t55,f4.1,t60,f4.0,t65,f4.1,t7.0,f4.0,t75,f 6 4.1) 2100 format(lx,a5,i2,1x,i3,i2,2x,i3,i4,lx,i2,2x,i3,i4) end Compilation statistics for procedure: reform Number of errors:

Procedure number:

1 0

Number of Warnings:

0 Accumulated number of source lines read:

180

A Conversion of Pilgrm Nuclear Power Station A1996-2001 Meteorological Data for Use With ARCON96 A R EVA Prepared by: Theodore A. Messier Framatome ANP. Inc.. an AREVA and Siemens companv Document ID 32-5052125.00 Page 13 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 09:34:45 2004 reform.f Page 5

CROSS REFERENCE LISTING:

Symbol File Function Line banner date delt dh dt reform.f reform.f reform.f reform.f reform. f iday reform. f ident ihour ilwd reform. f reform.f reform.f ilws imonth inf ile iseq istab iuwd iuWS iyear juldate j ulday2 leap lwd lws mod nint outf ile reform()

temp today uwd uws reform.f reform.f reform.f reform.f reform.f reform. f reform.f reform.f reform. f reform.!

reform.f reform.f reform. f reform. f reform.f reform.f reform.f reform.f reform.!

reform.f reform.f reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform reform

19 24 34 37 42

21 58 137 138 144 137 139 144 145 147 149 151 153 157 58 60 67 68 70 72 73 74 75 76 79 81 82 83 84 87 88 89 90 97

19 23 162 58 97 162 127 128 129 131 162 106 108 162 58 67 68 70 71 73 74 75 76 77 81 82 83 84 85 88 89 90 97

19 30 31 32 33 50 56 57 61 93 141 146 148 150 152 154 156 158 119 120 121 123 162 112 114 162 58 97 162 67 68 70 71 72 74 75 76 77 78 82 83 84 85 86 89 90 94 162 93 94

19 46 47 50 69

21 58 126 127

21 58 105 106 120 128 106 112 119 127

19 33 35 50

1

21 58

20 42 50

21 58 118 119

21 58 111 112 155 71 77 78 85 86 72 78 79 86 *87 34 162 73 79 81 87 88

A AR EVA Conversion of Pilgrm Nuclear Power Sta6on 1996-2001 Meteorological Data for Use With ARCON96 Prepared by: Theodore k Messier Franatome ANP. Inc.. anAREVA and Siemens comDan Document ID 32-5052125-00 Page 14 HP FORTRAN 77 Ver: B.10.20 Tue Oct 19 09:34:45 2004 reform.f Page 6

SYMBOL TABLE LISTING:

Symbol Class Type Offset/Size banner date ()

delt dh dt iday ident ihour ilwd ilws imonth infile iseq istab iuwd iuws iyear juldate julday2 leap lwd lws mod()

nint ()

outfile reform()

temp today uwd uws Variable Procedure: intrinsic Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Variable Procedure: intrinsic Procedure: intrinsic Variable Procedure: this func.

Variable Variable Variable Variable Character Subroutine Real*4 Real*4 Real*4 Integer*4 Character Integer*4 Integer*4 Integer*4 Integer*4 Character Integer*4 Integer*4 Integer*4 Integer*4 Integer*4 Integer*4 Integer*4 Character Real*4 Real*4 Character Subroutine Real*4 Character Real*4 Real*4 Local: SP -696 Local: SP -228 Local: SP -144 Local: SP -148 Local: SP -256 Local: SP -704 Local: SP -252 Local: SP -152 Local: SP -172 Local: SP -260 Local: SP -584 Local: SP -268 Local: SP -140 Local: SP -156 Local: SP -160 Local: SP -264 Local: SP -224 Local: SP -220 Local: SP -272 Local: SP -240 Local: SP -236 Local: SP -400 Local:

Local:

SP SP SP SP

-232

-336

-248

-244 Label Asm. Label Type 50 Lll Executable 60 L13 Format 80 L14 Executable 82 L15 Format 100 L16 Executable 200 L17 Executable 300 L18 Executable 400 L12 Executable 2000 L19 Format 2100 L20 Format Line Number(s) 27*

39*

45*

51*

57*

162*

166*

173*

177*

179*

32 171 38 47 50 62 164 142 58 31 58 162 Final Compilation Statistics for file: reform.f Accumulated errors:

0 Number of Warnings:

0 Total number of procedures:

1 Accumulated number of source lines read:

180 Timing Statistics for:

f77passl:

real:

0.17s user:

0.00s sys:

0.00s

A ARE VA Conversion of Pilgrrn Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96 Prepared by'. Theodore A. Messier Franmatomc ANP. Inc.. an AREVA and Siemens company Document ID 32-5052125-00 Page 15 ATTACHMENT B: COMPUTER INPUT AND OUTPUT FILES The following computer runs were carried out for this calculation:

reform 1996 PNPS 1996 meteorological data; input file bemet96.new; output files reform-banner.96 and pnps96.met 1997 PNPS 1997 meteorological data; input file bemet97.new; output files reform_.banner.97 and pnps 97. met 1998 PNPS 1998 meteorological data; input file bemet98.new; output files reformbanner.98 and pnps 98. met 1999 PNPS 1999 meteorological data; input file bemet99.new; output files reformbanner.99 and pnps 99. met 2000 PNPS 2000 meteorological data; input file bemetOO.new; output files reformbanner.O0 and pnps 00. met 2001 PNPS 2001 meteorological data; input file bemet0l.new; output files reformbanner.01 and pnps0 l.met Listing of Files Included on the Compact Disc and Transferred to the FANP COLD Server for Archival Storage File size in Bytes 693984 692088 693984 692088 692088 692088 316224 315360 316224 315360 315360 315360 13760 267 267 267 267 267 267 Date Time File Name File Description Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct Oct 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 09:27 09:27 09:26 09:27 09:27 09:27 09:35 09:35 09:35 09:35 09:35 09:35 09:34 09:35 09:35 09:35 09:35 09:35 09:35 bemetOO.new bemetOl.new bemet96.new bemet97.new bemet98.new bemet99.new pnpsOO.met pnpsOl.met pnps96.met pnps97.met pnps98.met pnps99.met reform.1 reform banner.00 reform-banner.01 reform banner.96 reform-banner. 97 reform banner.98 reform-banner.99 input 2000 meteorological data input 2001 meteorological data input 1996 meteorological data input 1997 meteorological data input 1998 meteorological data input 1999 meteorological data output 2000 meteorological data output 2001 meteorological data output 1996 meteorological data output 1997 meteorological data output 1998 meteorological data output 1999 meteorological data code listing for computer code reform banner output for reform using 2000 data banner output for reform using 2001 data banner output for reform using 1996 data banner output for reform using 1997 data banner output for reform using 1998 data banner output for reform using 1999 data Note: The time stamp for the files on the CD will be one hour less than shown above; this is due to the Windows XP operating system changing the time stamps of all files whenever Daylight Savings Time ends or begins.

A AR EVA Conversion of Pilgrmn Nuclear Power Station 1996-2001 Meteorological Data for Use With ARCON96 Prepared by: Theodore A. Messier Framatome ANP, Inc., an AREVA and Siemens company Document ID 32-5052125-00 Page 16 ATTACHMENT C: Validation of Computer Code reform Computer code reform was written to convert PNPS meteorological data into a format suitable for use with computer code ARCON96.

To test that the code functioned properly, some data were compared from the input and output files:

Inout 1996 Meteorological Data YR MN DY HR 96 3 13 22 96 1

1 1

96 1

1 2

96 1

1 10 96 1

1 9

96 1

6 13 96 1

6 12 96 2 15 10 UWD 217 310 310 5

UWS 65 106 88 181 126 158 195 9999 LWD 219 276 265 353 295 297 305 9999 LWS TEMP 68 36 40 32 35 33 93 35 53 36 80 15 70 14 9999 9999 DT 70 22 10

-12

-16

-18

-22 9999 327 292 297 9999 Converted 1996 Meteorological Data PNPS PNPS PNPS PNPS PNPS PNPS PNPS PNPS YR 96 96 96 96 96 96 96 96 JDHR 7322 1 1 1 2 110 1 9 613 612 4610

- LWD LWD SC 219 68 7

276 40 6

265 35 5

353 93 4

295 53 3

297 80 2

305 70 1

9999999 99 UWD UWS 217 65 310 106 310 88 5 181 327 126 292 158 297 195 9999999 The data comparison shows that the code correctly converted from year, month, day, hour to Julian Day, hour format.

Wind speed and wind direction values were converted correctly. Delta-temperature values were converted correctly to stability class (A=l, B=2, C=3, D=4, E=5, F=6, G=7, bad or missing=99). Wind speed and wind direction values flagged as bad or missing were correctly converted.

to 2.04.115 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Proposed Changes to the Pilgrim Technical Specifications Marked-Up and Insert Pages (13 pages)

TS Page 3/4.2-24 TS Page 3/4.7-11 TS Page 3/4.7-12 TS Page 3/4.7-13 TS Page 3/4.7-14 TS Page 3/4.7-15 TS Page 314.7-16 TS Bases Pages B3/4.7-1 0 8314.7-11 n A 3/4.7-12 Insert A to page B3/4.7-10 and Insert B to page B314.7-12 B3/4.7-13 Inserts C to page B314.7-13

I I

. PNPS TABLE 3.2.D RADIATION MONITORING SYSTEMS THAT INITIATE ANDIOR ISOLATE Minimum # of

(

' Operable Instrument Channels Per Trip system (1!

Trip Function Trip Level Settina Action (2) 2 2

Refuel Area Exhaust Monitors Refuel Area Exhaust Monitors

Upscale, <100 inrlhr Downscale A or B A or B I

NOTES FOR TABLE 3.2.1

1.

Whenever the systems are required to be operable, there shall be two operable or tripped trip systems. If this cannot be met, the Indicated action shall be taken.

2.

Action cak open

l sD A.

Ceaseoeri e e B.

Isolate sec ary con ainmentand start e standby gas treatment systen\\,

den 199 Amen ent N. Nj.4-7-2--

314.2-24

~.

.*.---b-a,......

LIMiTING CONDITiOtS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.)

A.

Primary Containment (Cont.)

With no H2 analyzer operable, reactor operation is allowed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If one of the inoperable analyzers is not made fully operable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . the reactor shall be in at least Hot Shutdown within the next.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.7 CONTAINMENT SYSTEMS (Cont.)

B.

Standbv Gas Treatment System and Control Room Hich Efficiencv Air Filtration Svstem

1. Standby Gas T reatment System

a. Except as specified in 3.7.B.1.c or 3.7.B.l.e below, both trains of the.

standby gas treatment shall be operable when in the Run, Startup, and Hot Shutdown MODES, during A movement offrradi-aed fuel assemblies in the secondary lcontainment,fano B-ring !Fovement spent fudl pool, And durirRg CORE ALTERATIONS.

lano curing operations with a potential for draining the reactor vessel (OPDRVs),

or the reactor shall-be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

b. 1. The results of the in-place cold DOP tests on HEPA filters shall show >99% DOP removal. The results of halogenate-hydrocarbon tests on charcoal adsorber banks shall show

>99.9% halogenated hydrocarbon removal.

S.

Standby tv-s Tr-atment Svstem and Control Room Hioh Efficiencv Air Filtration Svstem

1. Standby Gas Treatment System

a. 1. At least once per operating cycle, it shall be demonstrated that pressure drop across the combined high efficiency filters and

~

charcoal adsorber banks is less

(

than 8 inches of water at 4000 cfm.

2. At least once per operating cycle, demonstrate that the inlet heaters on each train are operable and are capable of an output of at least 20 kW.

3. The tests and analysis of

-Specification 3.7.8.1.b. shall be performed at least once per operating cycle or following painting, fire or chemical release in any ventilation zone communicating with the system while the system is operating that could contaminate the HEPA filters or charcoal adsorbers.

4. At least once per operating cycle, automatic initiation of I

S Revision at 2,

226 Amnmn o 525, l

2 1, 1go;1 1110 87-4--

314.7-11

LIMING CONDITIONS FOR OPERATION 3.7 CONTAINMENT SYSTEMS (Cont.)

B. Standbv Gas Treatment Svstem and Control Room High Efficiencv Air Filtration System (Cont.)

b. 2. The results of the laboratory carbon sample analysis shall shbw each carbon adsorber bank is capable of >97.5% methyl Iodide removal at 70% R.H. and 86F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 and tested in accordance with ASTM D3803-

'1 99. The analysis results are to be verified as acceptable within 31 days after sample removal, or declare that train inoperable and take the actions specified in 3.7.B.1.c.

-e. From and after the date that one train of the Standby Gas Treatment System is made or found to be inoperable for ahy reason, continued reactor opratlr i

rraeateu rnew fuel hanln nrte soent -fuel DoO~

permissible only dunng tne succeeding seven days providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all active components of the other standby gas treatment train are verified to be operable and the diesel generator associated with the operable train is operable.

SURVEILLANCE REQUIREMENTS 4.7 CONTAIN\\MENT SYSTEMS (Cont.)

B. StandbV Gas Treatment System and Control Room High Efficiencv Air Filtration System (Cont.)

each branch of the standby gas treatment system shall be demonstrated, with Specification 3.7.B.1.d satisfied.

5. Each train of the standby gas treatment system shall be operated for at least 15 minutes per month.

S. The tests and analysis of Specification 3.7.B.i.b.2 shall be performed after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation.

b. 1...ln-place cold DOP testing shall be performed on the HEPA filters after each orompleted or partial replacement of the HEPA filter bank and after any structural maintenance on the HEPA filter system housing which could affect the HEPA filter bank bypass leakage.

H2.

alogenated hydrocarbon testing shall be perf6rmed on the charcoal adsorber bank after each partial or complete replacement of the charcoal adsorber bank or after any structural maintenance on the charcoal adsorber housing which could affect the charcoal adsorber bank bypass leakage.

If the system is not made fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutd jhe next 36h n tue

0.

s shaBll be Fuel handling operations in progress may be complex ted.

Amendmenlt No. 12. 50, 2, 114, 1E4, E6I,

i170, 4tr-314.7-12

LTM7TTNG CONDMONS FOR OPERAtVON 3.7 CONTAINMBT SYSTERS (coat) gURVETLLANCE REOMREENNS 4.7 CONTA&IMENT SYSTEMS (Conat)

B.

-dbv -

-Trtmmt Svte'm and Control Ro:rn H9i Efiescv iir Eiltraion StI (Cont.)

B.

Eiandbv G2s Trmtent Svwtem and Control gom Uigh Efficiecv Air Fiiraton System (Cont.)

d.

Fans shall opratc within

10% of 4000 cfm.

From and mftr the

-te one me of the Standby Gas Trtmcnt Sysn is made or found to be inopernble for anp g u

~

esan proiding thiat witin 2 hour3 aDl acdve componzmnt of th: other train are verified to be opeablk and dh:

diesel gmetor associated with the op.-rable train is operable.

L6-

. f/e.Q C fOWs) lf the system is not made fully optrable within 7 days, i) piat the operablc train in op::aion in diateiy or; ii) suspend movemet Do ;

fuel assemblies in secoDdmry conthinmepent fue hpoo ornc tovr tiEi speat fuel pool or cc Wny fuelasbly movbemnt in nprogtes many be completed.

Amendment No.'2 C, t, 1Gli l 1R..

VV.*

15, L.

34I7 3 314.7 13

LIMITING CONDITIONS FOR OPERATION

,3.7 CONTAINMENT SYSTEMS (Cont.)

B. Standby Gas Treatment System and Control Room Hich Etticiencv Air Filtration System (Comn.)

2. Control Room High Efficiency Air Filtration Svstem SURVEILLANCE REOUIREMENTS 4.7 CONTAINMENT SYSTEMS.(Cont.)

B. Standby Gas Treatment System and Control Room Hich Efficiencv Air iltration Svstem (Cont.)

a. Except es specified in Specification 3.7.B.2.c or 3.7.B.2.e below, both trains of the Control Room High Efficiency Air Filtration System used for the processing of inlet air to the control room under accident conditions shall be operable when in the Run, Startup, and Hiot Shutdown MODES, during movement of irradiated fuel assemblies in the secondary containment a uring eover he spent fuel pool, and durin Aand during Emotions wita potential f or draining the reactor vessel (OPDRVs),

or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Control Room Hiob Efficiency Air Filtration Svstem

a. At least once per operating cycle the pressure drop across each combined filter train shall be demonstrated to be less than 6 inches of water at 1000 cam or the calculated equivalent.

b.- 1. The tests and analysis of Specifications 3.7.8.2.b shall be performed once per operating cycle or following painting, fire or.

chemical release in any ventilation zone communicating with the system while the system is operatng.

/

b..1. The results of the in-place cold DOP tests on.HEPA filters shall

.show Fot9% DOP removal. The results of the halogenated hydrocarbon tests on-charcoal adsorber banks shall show Z29.9%

halogenated hydrocarbon removal when test results ate extrapolated to the initiation of the test.

2. The results of the laboratory carbon sample analysis shall show

Ža97.5S methyl iodide removal at 70% R.H. and 860F. The carbon sample shall be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 19F&and tested in accordance with ASTM D3803-1989. The analysis results are to be verified as acceptable within 31 days after sample removal, or declare that train inoperable and take the actions specified in 3.7.8.2.c.

A

2. In-place cold DO? testing shall be performed alier each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing which could affect the HEPA filter bank bypass leakage.

3. Halogenated hydrocarbon testiog shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakage.

4. Each train shahi be operated with the heaters in artomatic for a: least 15 mrinutes every month.

314.7-14

LTING CONDITIONS FOR OPERAFTON 3.7 CONTAINhMET SYSEMS (Coat)

SUJRVWLILANCE RSOUlEENT.s B.

Standbv Gas Trmttnent Svs=n and Control Room High fE cimcv Air Filtration Sytem (Cort.)

4.7 cO1TAIQ{ENT SYSTEMS (Cant.)

B.

Standbv Gas Trntt Svsten and Contl Room Hh;h Effi

' Air Firatio S% -,I =

5. Tne t=-and =aaisis of cc:=ion3.?.3r.b. shall

!>'- p=O=.Zd daftr cver

.7 0 hour0 days 0 hours 0 weeks 0 months . f ryrten on:rjion.

I.

'F rom =nd aft-r th: dte ah= cc: UIn oid th: Conro! RFoom Hiin -=-i-ey Air Filr=non Svsr:;n is made or found to te inop:rable for-any r-soL. r:tor t-uzciue handlast over th1 Set i

2 S epmisib~D]olyduring the

-SUCeding 7 dayS providng dtat. within 2 bours all actire componts of the otbz: CREAF trn are vrified to be operable and the dieslc geeat=or ass;X iated with di oezbk train is op.ablc. If ihe systan is not made fully operable within 7 days, rector shutdown shaOl be ira; and the r=:tor sall be in cold shutdown within the n= 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months h

1 oueauOns Fuel h tlnjaithin.

1 thoUS!. Fu1bd lneoperaton in_~

Qr~csraab o

p Ctcn npr ope.4ing cycie d.L-nrcsz-"

that tl. inlet h.t.:

on eh nan 5r operable and canable of an ouxmU of at Iezt 14

d.

Pcro.;n an irnstrurnnt funv-ioml test on tL-huntidirtss controlling EL beaters once per operating cyclc.

d.. Fans shalfl op:rat5e vutin e 10% of

.1000 CfM.

c-FrDM and after the daie that one -

t-i of tll: Ccntro1 R~OOM Hi'71

/

out Effinency Air Filtraion Syste is mad: or found to b inoprable for any osung tMAuedi zes 7

day.

. e o

g~da s

p^

dwdayea providing that within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months all hc Q

acovc componeats of the other-'

train are verified to b^ oernble-and the dl l gn=:ator Associated with !he operable arain is operable.

If the systan is not made fully operable Vwthin 7 dsvs evrion 19 Amendment No.

73147-15 I

. fini 1n mCONDTONS FOR OPEBAITON SURFLLANCrSE REQUIREMI:N-r 3.7 COTAW ENTSTBMS (Cont.)

4.7 QQWTA WSY51 - MHS (oat.)

i) p=

surveillanee 4.7.B.2.b.4 for d=

oprable CR.iEAF very 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months L) Id SUV==t 0N i%:01 as~nues n s-oadzv iotad r~

TAny fui s:znbiy rnomc.=t in Progcss may be complred.

.Ap Wit k

q 5; LAc:deg Rs.

C.

Stodzry Crtinment C.

Secondary C&ontinM:t

'1

1. Secondary coatainmnt shall be OPERABLE mi= in the Run, Startup and Hot Shutdown MODES, during movcmnet o!a t

_ar assemblies in the secndary contzinm=

durig opeasons ari-potnrzai for zmng the r.ator ves1 (OPDRVs).

1. Each r=-Ieing outage prior to refueling, Sccondasy containrnt capability shll be dcrnomsted to maintain 114 inch of water vacuum Under calmr wind (5 mph) condiions with a filtr zinflow of not more tbn 4000 cfin.

2. a. With Secodazy Contairmet inoperable vhri in the Run, Starmp and Hot Shutdown MODES, rtome Secondary Containctit to OPERABLE stzaus.within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. Pzuircd Action and Complution Tim of 2A not mert be in hot Shutdowi in 12 bours A

Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

I

c. With Secondary Contnnt inoperable during movent o tsenblies in the secondary cuiung mno~vmemi or new uel ovzr ih L

t l pool, and dusin CO ALTRa7 and during OPDRVs,,

hnrnedianely

1. Suspend movement a

atzd fuel zsesmblis in the secondary cotzinmnt.

\\

~AND I

3 Ss~

CORE AITEE-R-ONTS.

L/

Inidate ationsto suspend OPDRVs.

ev 1

o 3

34.7-1 6

314.7 CONTA1NMENT SYSTEMS (Cont.)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five ycars leads to only minor decreases in methyl iodide removal flciency. Hence, the f-equency of laboratory carbon sample analysis is adequate to demonstrate acceptability. Since adsorbers must be removed to perform this analysis this fiequency also minimizes the system out of service time as a result of surveillance testing. In addition, alhough the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known efciency and holding capacity for elemental iodine andlor methyl iodide, the testing also gives an indication of the relative efficiecy of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its designed finction is demonstrated and known in a timely manncr.

Th1 required Standby Gas Treate System flow rate is that flow, less than or equal to 4000 CFM which is needed to maintain the Reactor Building at a 0.25 inch of water negative pressure upder calm wind conditions. This capability is adequately demonstrated during Secondary Containment Leak Rate Testing performed pursuant to Technical Specification 4.7.C.l.c.

Ihe test fiequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.

The filter testing is performed pursuant to appropriate procedures reviewed and approved by the.

-Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are pcrformed to detect plugging or leak paths though the filter or adsorber nedia. Considering the relatively short times the fims will be un for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorbers-.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintain the secondary contait at a 0.25.inch of water negative pressure upon containment isolation. If one system is rnade or found to be inoperable, there is no imuediate threat to the containment system performance and reactor operation or refueling activities may continue while repairs are being made. In the event one SBGTS is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This substantiates the availability of the operable system and justifies continued reactor or refueling operations.

flutng efueingoutages, if the inoperable train is not restored to operable status within the required completion time, the operable train should immediately be plaed in operation. This action ensures that the remaining train is operable, that no filures that could prevnt automatic actation have occurred, and that any other filure would be readily detected. An alternative is to suspend fuel movement, thus, placing the Revision1 meniiminNo.

7~4,-l l-!

i70 JB 314.7.10

. BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont) bot tain o rS are inop iah tftuepat=

s Fro~ught t-oa 'condition whiere the) t SNGT isnot required..

B.2 Control Room High Efficiency Air Filtration System The Control Room High Efficiency Air Filtration System is designed to filter intake air for the control room atmosphere during conditions when normal intake air may be contaminated. Following manual initiation, the Control Room High Efficiency Air Filtration System is designed to position dampers and start fans which divert the normal air flow through charcoal adsorbers before it reaches the control room.

High Efficiency Particulate Air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radiolodine to the control room. A second bank ofHEPA filters is installed downstream of the charcoal filter.

The in-place test results should Indicate a system leak tightness of less than 0.1 % bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99% removal of cold DOP particulates. The laboratory carbon sample test results should indicate a methyl iodide removal efficiency of at least 97.5% for expected accident conditions. Tests of Impregnated charcoal identical to that used In the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodine removal efficiency. Hence, the frequency of laboratory carbon sample analysis is adequate to demonstrate acceptability.

Since adsorbers must be removed to perform this analysis, this frequency also minimizes the system out bf service time as a result of surveillance testing. In.addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known'efficiency and holding capacity for elemental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform Its designed function is demonstrated and known in a timely manner._.

Determination of the system pressure drop once per operating cycle provides indication that the HEPA filters and charcoal adsorbers are not clogged by excessive amounts of foreign matter and that no bypass routes through the filters or adsorbers had developed.

Considering the relatively short times the systems will be operated for test purposes, plugging is unlikely and the test interval of once per operating cycle is-reasonable.

Revis1 78 me=etN.4~A42 B3/4.7-1 1 J

INSERT"A"TO PAGE B314.7-10 As discussed In Bases Section B3/4.7.C "Secondary Containment', SGTS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified decay period ie., no longer "recently irradiated.

During movement of recently Irradiated fuel, if one train of SGTS is made or found to be inoperable and the inoperable train is not restored to operable status within the required completion time, the operable train should immediately be placed in operation, This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative is to suspend movement of recently irradiated fuel, thus, placing the plant in a condition that minimizes risk. If both trains of SBGTS are inoperable, the plant is brought to a condition where the SBGTS is not required.

INSERT "B" TO PAGE B3/4.7-12 As discussed in Bases Section B3/4. 7.C OSecondary Containmentr CRHEAFS is not required to be operable during movement of irradiated fuel assemblies that have been allowed to decay for the minimum specified dery period i.e., no longer recently irradiated'.

314.7 CONTAINMENT SYSTEMS (Cost)

B.2 Control Room High Efficiecy Ar Fil=ttion Sstem (COnt.)

The test frequenucies art adequate to detet equipment deterioration prior to significant defbcs, but the test are not fiequent enough to load the filters or adsorbers, thus reducing their reserve capacty too quickly.

The filter testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. Tbe in-place testing of charcoal filters is performed by injecting a halogenad hydrocarbon into the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concntrations gives an overall indication of the leak tightness of the system. A similar procedure substitting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA fihe.

I Air flow through the filtes and charcoal adsorbers for 15 minutes each montfh assures operability of the system. Since the system heaters are automatically controlled, the air flowing through the filters and adsotbers will be S70% relative humidity and will have the desired drying effect.

If one train of the system is made or found to be inoperable, there is no immediate threat to the control room, and reactor operation or fuel handling may continue for a limited period of time while repairs are being made. In the evt one CRBAF train is inoperable, the redundant system's active components will be verified to be operable within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . During refueling outages, if the inoperable train is not restored to operable stus within the required completion time, refueling operations nay continue provided the operable CRHEAF train is placed in the pressurization mode daily. This action ensures that the remaining vtain is operable, that no failures that would prevent action will occur, and that any active failure will be readily detected. An altemajive is to suspend activities that present a potentil for releasing radioa~tivity thit might require isolatioi of ihe control room. If both trains of the CRHEAF system are inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is not required.

ndmentNo.,

1 l70o B314.7 12

e 1A e Pes Ad my re-u act V-J/4.I LUN IAItNMtN 1-b YT I EMS (-Ofnt)

C.

Secondary Containment syste secondary conEtaunent Is reqignre at alnimes any ground ievel release of radio re ave ll lmaterials which mnight result from a serious accident. The reactor building provides secor contairnment during reactor operation, when the drywell is sualcd and in service. the r a;r bu Iin provides primary containment when the reactor is shutdoxn and the drywvell is oper a~uring refueling. Because the secondary containment is an integral part of the complete c pannnt s% stem. secondarv containmnent is required at all timnes that primary contai ment iyfqie as well as during refueling.

There are two principal accidents for which credit is taken for secondar co ent operability.

These are a loss of coolant accident (LOCA) and a fuel handling accident iside [secondary]

containment. The secondarv containment performas no active function sponse to each of these limiting events; however, its leak tightness is required to ensure that release of radioactive materials from the primary containment is restricted to those I paths and associated leakage rates assumed in the accident analysis and that fission products e pped within the secondary containment structure will be treated by the SGT System prior discharge to the environment.

An operable secondary containment provides a control vol into which fission products that bypass or leak from primary containment, or are released om the reactor coolant pressure boundary components located in secondary containmen can be diluted and processed prior to release to the environment. For the secondary contai ent to be considered operable. it must have adequate leak tightness to ensure that the required um can be established and maintained, If secondary containment is inoperable (when r ired to be operable), it must be restored to operable statu~ithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pletion time provides a period of time to correct the problem that is commensurate with the im ce of maintaining secondary containment during Run, Startup, and Hot Shutdown modes.

s time period also ensures that the probability of an accident (requiring secondary containm t operability) occurring during periods where secondary containment is inoperable is minimal.

If secondary containment canot b restored to operable status within the required completion time.

the plant must be brought to a m e in which the LCO does not apply. To achieve tUs status, the plant must be brought to at I Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed comple n times are reasonable, based on operating experience, to reach the required plant conditions m full power conditions in an orderlv manner and without challenging plant systens.

/

Movement of irradi d fuel assemblies in the secondary containment, movement of new fuel over the spent fuel pool ye alterations, and OPDRVs can be postulated to cause fission product release to the sec ndary containment. In such cases, the secondary containment is the only barrier to release of ion products to the environment. Core alterations, movement of irradiated fuel assemblies, d movement of new fuel over the spent fuel pool must be immediately suspended if the secon containment is inoperable.

Susp on of these activities shall not preclude completing an action that involves moving a corn nent to a saf: position. Also, action must be immediately initiated to suspend OPDRVs to ze the probability of a vessel draindomn and subsequent potential for fission product release.

ctions must continue until OPDRVs are suspended.

Initiating reactor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water negative pressure within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system. Functionally testing the initiating sensors and associated trip channels demonstrates the capability for automatic actuation.

Performing these tests prior to refueling will demonstrate secondary containment capability prior to the time the primary containment is opened for refueling. Periodic testing gives sufficient nfidence of reactor building integrity and standby gas treatment system performance capability.

Revision 81 nB3/4.7-13

INSERT "C" TO PAGE B3/4.7-13 The secondary containment is designed to minimize any ground level release of radioactive materials that might result from a serious accident. The reactor building provides secondary containment during reactor operation, when the drywell is sealed and in service; the reactor building provides primary containment during

-periods when the reactor is shutdown, the drywell is open, and activities are ongoing that require secondary containment to be operable. Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required as well as during movement of 'recently irradiated" fuel and during operations with the potential to drain the reactor vessel (OPDRV).

There are two principal accidents for which credit is taken for secondary containment operability. These are a loss of coolant accident (LOCA) although not specifically evaluated for alternate source term methodology and a fuel handling accident involving "recently irradiated fuel. The secondary containment performs no active function in response to each of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the Standby Gas Treatment System (SGTS) prior to discharge to the environment.

In addition to these limiting accidents, OPDRVs can be postulated to cause a fission product release. During movement of recently irradiated fuel and OPDRVs, secondary containment would be the only barrier to a release to the environment. Therefore, movement of recently irradiated fuel and OPDR Vs must be immediately suspended if the secondary containment is inoperable. Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDR Vs to minimize the probability of a vessel drain down and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

An operable secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment can be diluted and processed prior to release to the environment. For the secondary containment to be considered operable, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained.

If secondary containment is inoperable (when required to be operable), it must be restored to operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4-hour completion time provides a period of time to correct the problem that is commensurate with importance of maintaining secondary containment during Run, Startup, and Hot Shutdown modes. This time period also ensures that the probability of an accident (requiring secondary containment operability) occurring during periods where secondary containment is inoperable is minimal.

If secondary containment cannot be restored to operable status within the required completion time, the plant must be brought to a mode in which the LCO does not apply. To achieve this status during power operation, the plant must be brought to at least Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to Cold Shutdown within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power condition in an orderly manner and without challenging plant systems.

The Fuel Handling Accident (FHtA7nalysis is based on 10 CFR 50.67 and R.G. 1. 183 Alternate Source Term Methodology. This parametric analysis concluded that the calculated TEDE values to the control room occupants, the exclusion area boundary, and the low population zone are well below the allowable TEDE limits established in 10 CFR 50.67 without crediting Secondary Containment, SGTS and CRHEAFS as long as a the fuel is allowed to decay for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following reactor shutdown.

As a result, "Recently irradiated fuel is defined as fuel that has occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , i.e. reactor fuel that has decayed less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following reactor shutdown. Each fuel cycle, prior to the refueling outage, the decay period that must elapse prior to movement of irradiated fuel in the core will be re-evaluated to ensure the appropriate, minimum decay period is enforced to maintain the validity of the FHA dose consequence analysis.

Therefore, SGTS, CRHEAFS and Secondary Containment are not required to be operable during movement of decayed irradiated fuel that is no longer is considered "recently irradiated". Conversely, Secondary to 2.04.115 I

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Summary of Commitments Commitment ID Description

\\

Due Date

1.

Entergy will revise the Pilgrim guidelines for assessing Completed prior to systems removed from service during the handling of ' -the implementation non-recently irradiated fuel assemblies or core of this license alterations to implement the provisions of Section amendment.

11.3.6.5 of NUMARC 93-01, Revision 3.

2.

Revise Pilgrim UFSAR to reflect revised fuel handling Completed in analyses and alternate source term.

accordance with next scheduled FSAR update after approval of this application.

(1 page) to 2.04.115 I

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Plant Proposed Amendment to the Technical Specifications Response to NRC Request for Additional Information (7 pages)

Response to NRC Request for Additional Information NRC Question 1:

The April 14, 2004 submittal includes various radiological consequences analyses for the fuel handling accident (FHA) assuming that the damaged fuel has decayed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and assuming credit for filtration by the standby gas treatment system (SGTS) and/or the control room high efficiency air filtration system (CRHEAFS).

a.

For the analyses that credit CRHEAFS operation, give the basis for the control room envelope unfiltered inleakage assumption of 500 cfm. Has testing been performed to verify this assumption?

b.

For the analyses that credit SGTS operation, what is the design SGTS flow rate that would be expected for the design basis FHA? This is not the modeling assumption that allows for the release to the environment in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , but the actual flow rate.

Response

The revised calculation for the radiological consequences of a fuel handling accident no longer credits CRHEAFS or SGTS.

NRC Question 2:

The April 14, 2004 submittal includes various FHA analyses to show that after the fuel has decayed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , no filtration credit for the SGTS or CRHEAFS is necessary to meet the regulatory dose acceptance criteria. Is movement of the fuel expected to occur prior to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the reactor has shut down?

Are there any technical specifications or administrative controls at Pilgrim that apply to when fuel movement is allowed post shutdown?

Response

The revised FHA demonstrates that after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay, SGTS and CRHEAFS filtrations are not necessary to comply with the regulatory acceptance criteria.

It is not considered credible to move fuel with less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay. This assumption will be included in the revised FSAR discussion of this analysis.

NRC Question 3:

On page 26 of Attachment 1 of the April 14, 2004 submittal, Pilgrim commits to implement the provisions of Section 11.3.6.5 of NUMARC 93-01, "Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," to address capabilities to promptly close secondary containment, as is consistent with TSTF-51. NUMARC 93-01 states in part that "these prompt methods need not completely block the penetrations nor be capable of resisting pressure, but are to enable the ventilation systems to draw from the postulated FHA such that it can be treated and monitored."

a.

Please describe the prompt methods including time required to close and the degree of closure that will be achieved.

b.

How much of an open area to the environment would be permitted?

I

c.

Also describe the ventilation systems that would be used to draw the release from the postulated FHA.

Specifically, are the ventilation systems engineered safety feature systems, do they have carbon adsorber filters and high-efficiency particulate air filters, are they tested in accordance with Regulatory Guide (RG) 1.52 or other standards, and do they have sufficient drawing capacity to assure that air flow is from environment to the containment?

d. Would there be a test to determine that all air flow was into the containment in the event that the Pilgrim procedure allows partial closure?

e.

Other licensees have provided information on how they intend to meet the recommendations and made specific notation of the requirement in the Technical Specifications to close the containment in the event of an FHA. Does Pilgrim have the capability to make a similar commitment?

Response

10 CFR 50.65(a)(4) requires Pilgrim to assess and manage changes in risk that result from taking risk-significant systems out-of-service or during certain maintenance activities. The NRC staff, in Regulatory Guide 1.182 states that the methods detailed in Section 11 of NUMARC 93-01 are acceptable for complying with the requirements of 10 CFR 50.65(a)(4).

Pilgrim has implemented a Configuration Risk Management Program (Technical Specification 5.5.7) for assessing changes in risk that could result from taking risk-significant systems out-of-service during maintenance activities. This program, which was reviewed and approved by the NRC for Operating License Amendment 187, follows the requirements of 10 CFR 50.65(a)(4) and Section 11 of NUMARC 93-01. Pilgrim has implemented this program through plant procedures 1.5.22, "Risk Assessment Process" and 8.M.1-45, "Outage Shutdown Risk Assessment".

Accordingly, Pilgrim develops risk profile associated with the plant configuration and implements administrative controls prior to removing risk-significant systems or equipment for service using procedure 1.5.22. This qualitative and quantitative process is followed during refueling outages to determine shutdown risk profile to ensure plant configuration remains in the least risk-significant condition. The scope and type of administrative controls are developed based upon the type of risk-significant system being removed from service and system alignment requirements for available systems to remain in the least risk-significant condition.

The outage shutdown risk assessment procedure (8.M.1-45) establishes the methodology for conducting a planned outage safety review to reduce the likelihood and/or consequences of an adverse event during planned outage. This methodology follows the guidance of NUMARC 91-06, "Guidelines for Industry Actions to Assess Shutdown Management". In accordance with this procedure, Pilgrim develops a contingency plan - an approved plan of compensatory actions -

to maintain and restore defense-in-depth system availability when system availability drops below the level planned for the outage and to minimize the likelihood of loss of a key safety function during high risk evolution.

This contingency plan addresses the plant-specific configuration taking into account the planned system maintenance and refueling operational activities, such that, if a fuel handling accident were to take place, system alignments, administrative controls, and compensatory measures will be employed to minimize the release of radioactivity to the environment.

Response to a, b, and c:

After the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months decay time, Pilgrim plans to allow the reactor building truck lock doors to be opened to the environment to facilitate ingress and egress, and transfer of heavy equipment 2

when necessary. The truck lock door area is the largest opening in the secondary containment, which is approximately 400 sq. ft. (20ft x20 ft) and has two 20x20 ft inside and outside doors separated by about 125 ft distance and are easily closed. The truck lock opening doors control the ingress and egress to the security vital area and radiological control area (RCA). Normally, at any time during refueling outage only one door will be opened at any time. Both doors will be kept open for a very short time in order to facilitate the transit of equipment. During refueling outage, the truck lock door area is continually manned or monitored by a member of the security force since it potentially allows access to vital area and the RCA. In addition to the truck lock opening, Pilgrim may cut out openings or penetrations into the secondary containment walls to facilitate large equipment removal and installation; however, such openings or penetrations would not be larger than 20X20 ft, and would be cut out only on an as need basis and will be closed after their use.

The area radiation monitors on the refueling floor provide indication for prompt actions in the event of a fuel handling accident. In the event of a fuel handling accident, the radiation monitor high range set point initiates the secondary containment isolation through the reactor building isolation and control system (RBICS). The RBICS serves to trip the reactor building supply and exhaust fans, isolate the normal ventilation system, and provide for SGTS starting signal, as described in FSAR Section 5.3. Following initiation, the reactor building ventilation isolation dampers close within a specified time (3 sec) to prevent release of radioactive material from the secondary containment. The refueling floor exhaust isolation dampers must close in 3 sec to isolate the most direct path outside the secondary containment. The RBICS also automatically trips the reactor building supply and exhaust fans and starts the SGTS. The normal design flow rate in the reactor building operating (refueling) floor exhaust duct is 40,000 cfm.

During shutdown the flow rate is increased to approximately 50,000 cfm, at which time it takes more than 3 sec for the fission products released in any postulated fuel handling accident to travel from the operating (refueling) floor ventilation exhaust radiation monitors to the isolation dampers. Thus, no direct release of fission products to the environment (by passing the SGTS filtration process and the elevated release point provided by the main stack) is possible. Prompt action initiated by the RBICS assures that the radioactive flume remains on the refueling floor and exhausts through the SGTS filtration system when this equipment is available.

Even though SGTS and CRHEAFS are not required to be operable to comply with the NRC acceptance criteria in the event of a fuel handling accident after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay, to minimize the dose consequences from release of radioactivity, Pilgrim will follow these steps:

1. Promptly close the truck lock doors and any other cutout openings in the secondary containment, and secure the secondary containment atmosphere.

2. Align the available SGTS filtration system and place it in operation. Normally only one train will be removed for maintenance and the other train will be available.

3. If both SGTS trains are out of service (a worst-case scenario), Reactor Building Heating and Ventilation System (RBHVS) may be manually started and placed in operation to vent the building unless it isolated on a high radiation signal. Until the RBHVS is placed in operation, the radioactive plume would remain on the refueling floor since the truck lock doors and cutout openings in the secondary containment would be closed and the refueling floor atmosphere would be at the outside environment pressure and there would be no significant air movement in or out of the building. As described in FSAR, Section 10.9.3.3, the RBHVS is divided into three major ventilation zones.

The operating floor ventilation encompasses the refueling floor atmosphere and has sufficient drawing capacity (2 fans) to assure that airflow from environment to the containment takes place and the refueling floor atmosphere exhausts through the unfiltered reactor building vent. The RBHVS does not have charcoal adsorber filtration system. FHA 3

analyses demonstrate that the dose consequences from the unfiltered plume are below the regulatory acceptance limits to the occupants in the control room, LPZ, and EAB after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay time.

Response to d:

There would be no test to determine the airflow to the containment. The design of the reactor building operating floor ventilation encompasses the refueling floor atmosphere and has sufficient drawing capacity (2 fans) to assure that airflow from environment to the containment takes place, as described in FSAR Section 10.9.3.3.

Response to e:

Pilgrim has committed to implement the provisions of Section 11.3.6.5 of NUMARC 93-01 (See ) to address capabilities to promptly close secondary containment, but does not make any new commitments or notations to the Technical Specifications, as they are not needed. The current and the proposed Technical Specifications requires Pilgrim to maintain the integrity of the secondary containment during the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following subcriticality and follows the prompt response actions as discussed above in the event of a fuel handling accident after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of achieving subcriticality.

NRC Question 4:

Confirm that, overall, the meteorological data used in the assessment are of high quality, suitable for use in the assessment of atmospheric dispersion to which it was applied, and provide an electronic copy of the hourly meteorological measurements on the docket.* Does the collection program meet RG 1.23, 'Onsite Meteorological Programs," guidelines? During the period of data collection, was the tower base area on a natural surface (e.g., short natural vegetation) and was the tower free from obstructions (e.g., trees, structures, terrain) and micro-scale influences to ensure that the data were representative of the overall site area? In the case of possible obstructions, were trees, structures, etc., at least 10 times their height away from the meteorological tower?

Were instruments and systems maintained within specifications? What types of quality assurance audits were performed on the meteorological measurement systems to ensure that data were of high quality and to identify any problems and questionable data and correct problems in a timely manner? What additional checks and at what frequency were the checks performed on data following collection, prior to archival, and following formatting for input into the analysis of atmospheric dispersion (e.g., using ARCON96)? If deviations occurred, describe such deviations and why the data are still deemed to be adequate. Were the data compared with other site historical or regional data? If so, what were the findings?

Response

The original submittal used data from both the 220-ft meteorological tower (Tower A) and the 160-ft meteorological tower (Tower B). The Tower B does not meet the meteorological siting criteria recommended by R.G. 1.23. The revised submittal uses the meteorological data only from the Tower A, which meets R.G. 1.23 meteorological siting criteria and effectively resolves the issues raised regarding the quality of the meteorological data.

The 220 ft Tower A is located approximately 430 meters WNW of the Reactor Building, on a vegetated hillside approximately 275 meters from the shoreline. The base of the tower is kept in a state of natural vegetation, with periodic brush clearing to maintain vegetation height at less than the 1OX height criterion. During the time period in question, routine sensor replacement was occurring on a quarterly (3-month) interval, using sensors calibrated at the vendor facility 4

traceable to NIST standards. Qualitative checks (wind direction alignment to cardinal sectors, ice bath tests for temperature sensors, etc.) were performed during these quarterly calibration/equipment exchanges. Pilgrim also performed daily quality screening of data to look for grossly anomalous or missing data, as well as weekly zero and span calibration checks of equipment. Monthly data sets were edited to indicate invalid data flags for calibrations and known sensor malfunctions. These monthly data files were then submitted to a contractor for processing of joint frequency distribution and X/Q calculations.

As part of this contracted service, data were screened using NUREG-0917 quality screening criteria. The data for the five-year period 1996-2000 used in the ARCON and AEOLUS runs were re-screened using NUREG-0917 criteria and found to be suitable for use. Overall data recovery for the six-year period was approximately 94%, with the lowest recovery during any individual year being 90.8%.

Joint frequency distributions (JFD) calculated from the 1996-2001 period were compared to historical JFD data for the years 1992 and 1993 and found to be comparable.

Although six years of meteorological data were evaluated for suitability, only the five-year data set from 1996 through 2000 was used in calculations of X/Q values.

NRC Question 5:

Staff review indicates some apparent anomalies in the 1996 through 2000 meteorological data as submitted. The following are provided as examples. Therefore, please check the data and confirm that the data as provided are of high quality or amend the file(s) as appropriate. If an amendment is needed, provide a copy of the revised file(s), the basis for acceptability of any residual departures from typical conditions and RG 1.23, "Onsite Meteorological Programs," and the revised X1Q values, if appropriate.

a) Why were there several periods of relatively long data outage (e.g., more than a week)?

Have changes been implemented to address conditions causing such outages?

b) With regard to general data formatting, how are invalid atmospheric stability data identified? Is the wind data for Pilgrim A 1999 transposed with upper level values in the lower level columns and vise versa?

c) Staff acknowledges Pilgrim A data were measured at the 67.1 and 10.1 meter levels on one tower and Pilgrim B data were measured at the 48.8 and 10.1 meter levels on a second tower. In the following questions, the tower used to measure Pilgrim A data will be called Tower A and the tower used to measure Pilgrim B data will be called Tower B.

Where are the two towers located? Does the difference in location result in differences in the measurements (e.g., due to terrain) and, if so, under what conditions are the differences likely to occur? What is the resultant impact on the X/Q values?

d) With regard to atmospheric stability, there appears to be a higher reported occurrence of stability class A on Tower A, between the 67.1 and 10.1 meter levels (about 25%), as compared to measurements on Tower B, between the 48.8 and 10.1 meter levels (14%).

Generally, for measurements on a single tower, one would expect a higher occurrence of class A conditions between the narrower measurement interval than between the wider measurement interval. Similarly, neutral conditions were reported to occur slightly more frequently on Tower B, over the narrower measurement interval, than on Tower A, over the wider measurement interval. Further, the 25% average for the Pilgrim A data is slightly higher than the averages for classes D and E. Why does class A occur so frequently?

Regarding the Pilgrim B data, there appears to be considerable year-to-year variability in a couple of cases in the occurrence of classes A and G. To what is this attributed?

5

In both the Pilgrim A and B files, multiple lengthy occurrences of both class A and class G are reported. The longest occurrence of class A is approximately 374 hours0.00433 days 0.104 hours 6.183862e-4 weeks 1.42307e-4 months and class G is 2489 hours0.0288 days 0.691 hours 0.00412 weeks 9.470645e-4 months . Is some of this data invalid? Also, in general, there was a relatively large number of occurrences of unstable conditions reported at night and stable conditions during the day. Since unstable conditions typically tend to occur during the daytime and stable conditions at night at many sites, what factors contributed to the occurrence of unstable conditions at night and stable conditions during the day at the Pilgrim?

e) The reported Pilgrim B wind speeds at the 10.1 meter level appear to be somewhat higher than the 10.1 meter Pilgrim A data. To what is that attributed?

Response to 5.a, b. c. d. and e.

As previously stated, the revised calculations use Tower A meteorological data, which meets the siting criteria recommended in R.G. 1.23. The revised calculations do not use Tower B data, as such the above-identified discrepancies and the apparent anomalies in the meteorological data are resolved by using the Tower A data. The annual data recoveries for Tower A for the six-year period 1996-2001 ranged from 90.8% to 97.1%, and averaged 94.3%

for the entire period. In most cases involving Tower A, failed meteorological sensors were replaced within one to two days of the problem being identified. If the specific time of failure could not be identified, data immediately prior to failure identification were evaluated, and were flagged invalid if the data were suspect. In the data processed for the re-submittal, Class A stability occurred 13% of the time, comparable to frequencies for this class in years preceding and following the six-year period in question.

Using the same six-year data set, Class D occurred 30% of the time, while Class.E occurred 35% of the time. The enclosed disk provides the Tower A meteorological data used in the revised calculations. Although six years of meteorological data was evaluated for suitability, only five-year data set from 1996 through 2000 was used in calculations of X/Q values. In all data sets all invalid data are flagged with a value of "9999".

NRC Question 6:

Provide a figure or figures showing structures, assumed paths of air flow, dimensions, heights and distances used as input in estimating the postulated transport of effluent from each of the release locations to the receptors. Are all directional inputs defined in terms of true north? If the figures are drawn in relation to plant or magnetic north, what is the relationship to true north, assuming that the meteorological measurements are based upon true north?

Response

The enclosed Pilgrim site plan provides the relative locations of the buildings and stack.

NRC Question 7:

If more than one release to the environment/transport scenario could occur (e.g., loss of offsite power and non-loss of site power, single failure), were comparative X/Q calculations made to ensure consideration of the limiting dose?

Response

6

Reactor building vent release without filtration is the most is the limiting scenario. The potential releases through the reactor building truck lock door lead to lower radiological impact.

Comparative X/Q values were used in each case, as shown in the revised calculations.

NRC Question 8:

Was RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," guidance used when making the X/Q estimates for the stack release to the control room air intake? Were the ARCON96 X/Q values always the more limiting case?

Response

R.G. 1.194 is used for the X/Q estimates for the stack release to the control room intake.

NRC Question 9:

The stack effluent vertical velocity is input into ARCON96 as 4.06 meters per second and stack flow as 1.7 cubic meters per second. Can this flow be maintained during the course of an accident (e.g., as addressed by technical specifications) even if a single failure or loss of offsite power occurs?

Response

The revised calculation no longer credits SGTS, thus this question is not applicable.

NRC Question 10:

Did dose estimates for the exclusion area boundary and low population zone use previously approved X/Q values? If so, provide a reference citation. If new X/Q values were calculated, provide a description of the methodology, inputs and assumptions used.

If the PAVAN (NUREG/CR-2858, "PAVAN: An Atmospheric Dispersion Program for Evaluating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations") computer code was used, provide a copy of the PAVAN input files.

Response

New X/Q values were calculated for the revised submittal. A copy of the calculation is attached, which provides the methodology, inputs, and assumptions used.

Encl:

Pilgrim Site Plan Drawings, C-1, Rev E2; C-2, Rev. E9; and A-105, Rev 2 7

DRAWING OR

FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:

DWG..NO. C-i, "SITE PLAN", REV. E2 WITHIN THIS PACKAGE..

OR BY SEARCHING USING THE DOCUMENT/REPORT NUMBER DWG. NO. C-i, REV. E2 D-O1

THIS PAGE IS AN

-OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:

DWG. NO. A-105, "ACCESS CONTROL & RADIATION

.ZONES GENERAL STATION YARD AREAS, OPERATION & SHUT DOWN", REV. 2 WITHIN THIS PACKAGE..

OR BY SEARCHING USING THE DOCUMENT/REPORT NUMBER DWG. NO.- A-i 05, REV. 2 D-02

THIS PAGE IS AN OVERSIZED DRAWING

-OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:

DWG. NO. C2, "SITE PLAN", REV. E9 WITHIN THIS PACKAGE..

OR BY SEARCHING USING THE DOCUMENT/REPORT NUMBER DWG. NO. C2, REV. E9 D-03 W

ML043650064

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