Text

1997 Annual Radioactive Effluent Release Rept
	ML20217P789
Person / Time
Site:	Seabrook
Issue date:	12/31/1997
From:	Anderson H, Kwasnik J, Leland W; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	;
Shared Package
ML20217P774	List: ML20217P771; ML20217P789;
References
	NUDOCS 9805070085
	Download: ML20217P789 (65)
	v • d • e

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SEABROOK STATION *

. . j PROCESS CONTROL PROGRAM

l (PCP)

SUBMITTED BY: // Aw" - M , dr 7

1. KWASNh, SENIOR RADIOLOGIDAL SCIENTIST DATE' r

REVIEWED BY: ////!/ ,

N,' STE DEPT. SUPERVISOR DATE APPROVED BY: &[/lO LM W.B. LELAND, CHEMISTRY & 14EALTH PHYSICS MGR, iN DATE 7

SORC REVIEW COMPLETED DURING MEETING NUMBER:h7"/3 DATE:

/ /d/!9,7 l REV. 01 9005070085 900430 PDR ADOCK 05000443 R PDR North Atlantic Enew Service Corporation t

Anpendix B Process Control Program Reauirement:

Technical Speci6 cation 6.12.2.a requires that licensee initiated changes to the Process Control Program be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the changes were made.

Resoonse:

The original Seabrook Station PCP was a vendor contracted service for mobile solidification. This PCP supponed the process of utilizing Seabrook Station's radwaste evaporator. Any waste concentrates would then have to be solidified prior to shipment off-site for burial. This mobile contracted process would then cover any solidi 6 cation that would be required.

In 1996, Seabrook Station implemented a PCP for the Snal dewatering of spent bead resin for off-site shipment and burial. As reported in the 1996 Annual Radioactive Ef6uent Release Report, the PCP was reviewed and approved by the Station SORC (96-042) on April 4,1996, and it superseded the original PCP. This PCP supported the fact that North Atlantic was utilizing resin cleanup systems for processing water rather than waste evaporators. Therefore, no waste concentrates would be generated and no solidification would be required. This change did not affect the overall conformance of the waste form as it related to the appropriate Federal and Burial Site requirements.

In 1997, North Atlantic revised the PCP (see attached) to include the processing of spent process Glters as part of the Seabrook Station dewatering envelope. This allows the dewatering of spent process Glters as well as spent bead resins. The PCP was also revised to modify the quali6ed bead resin approval list from speci6c manufacturers' types to resins that meet certain characteristics and conditions. These changes do not affect or reduce North Atlantic's ability to meet the appropriate Federal or Burial Site requirements for shipment and waste burial. This revision (revision 1) to the PCP was reviewed and approved by the Station's SORC (97-131) on October 1,1997.

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PROCESS CONTROL PROGRAM I. PURPOSE The Process Control Program (PCP) will assist in satisfying Nuclear Regulatory Commission (NRC) regulations and disposal site license requirements involving waste form structural stability and free-standine water limitations. As a minimum, these regulatory requirements are 10 CFR 61.56(a)(3)&(b) and the appropriate disposal site license requhements.

II. WASTE PROCESS DEWATERING USING THE " PUMP-AND-WAIT" DEWATERING METHOD AS ORIGINALLY DEVELOPED BY CHEM-NUCLEAR SYSTEMS INC.

1.0 GENERAL DESCRIPTION This section discusses the qualified waste, qualified equipment and procedures, and the acceptance criteria for dewatering radioactive waste using the " Pump and Wait" dewatering method as originally developed by Chem-Nuclear Systems, Inc. (CNSI). The Seabrook Station PCP is based on the NRC Branch Technical Position (BTP) on waste dated January 1991. The BTP ensures waste forms requiring stability consistently meet the stability requirements found in 10 CFR 61. The BTP only applies to waste forms where stability is required such as Class A-Stable, Class B, and Class C wastes. The Seabrook Station PCP does not address Class A - Unstable waste forms. Presently, the only waste form that needs to be processed according to the guidelines outlined in this PCP is depleted bead resin and process cartridge filters. The waste is loaded into an appropriate liner and dewatered by a cycle of eight hours of pumping out the excess water followed by an eight hour waiting period. The cycle is repeated until the appropriate number of dewatering cycles have been completed and the amount of water removed is below the value specified in Section 4.0, Acceptance Criteria.

2.0 PROCESS DESCRIPTION 2.1 SPENT RESINS 2.1.1 Seabrook Station will utilize the CNSI dewatering procedure for any required dewatering of spent bead resin or activated charcoal. This procedure is based on the CNSI Topical Report (DW-11118-01-NP-A) for process dewatering. The NRC reviewed and approved this document on June 11,1985. The CNSI dewatering procedure is a Radwaste Department instruction.

2.1.2 The dewatering process will utilize an air-driven positive displacement pump to obtain a continuous suction on the specified waste container. This process will remove any pumpable liquid to a predetermined end point. The cycle is repeated until the appropriate number of dewatering cycles is completed and the amount of water removed is below that set forth in the applicable criteria as stated in Section 61.56 (a) (3) and (b) (2) of 10 CFR Part 61.

2.1.3 Water removed from each waste container will then be retumed to plant systems for further processing - ifnecessary.

! PCP Rev. 01

2.1.4 The CNSI High Integrity Containers (HICs) that are used for wet layup resin storage will also be used in bead resin / charcoal dewatering. All dewatering procedures for ion exchange media or granular activated carbon are applicable for CNSI 14-215 or smaller l liners.

2.2 PROCESS FILTERS 2.2.1 Seabrook Station will ensure spent process filters sent off site for waste burial will meet all applicable requirements regarding freestanding water in the final waste form.

2.2.2 Seabrook Station will utilize Radwaste Department instruction WN0598.60, "CNSI Work Instruction for Verification of No Freestanding Water in a Filter HIC at Seabrook Station" to ensure compliance with step 2.2.1.

2.2.3 If exposure levels and/or conditions preclude the use of this instruction, Seabrook Station will utilize Health Physics Study / Technical Information Document (HPSTID)96-015,

" Natural Drying Times for Saturated Process Filters." This study evaluated the natural drying times for the three most common process filter types at Seabrook Station.

2.3 PROCEDURES AND EQUIPMENT 2.3.1 Station procedures must be consistent with applicable UFSAR and vendor operating

- procedures.

2.3.2 Dewatering equipment supplied by CNSI or other vendor shall meet the requirements of Reference 5.1. Equivalent substitutions may be made with the approval of the Radwaste Department Supervisor.

2.3.3 Waste containers shall meet the requirements of Reference 5.1 and the associated liner's !

procedure and UFSAR.

2.3.4 Prior to making significant modifications to the CNSI-provided dewatering equipment, waste containers, or operating procedures, CNSI shall verify in writing that such modifications are consistent with References 5.1,5.3, and/or 5.4, as applicable.

3.0 OUALIFIED WASTES 3.1 All bead resins and charcoals that are recommended and approved by CNSI and are designated as Advanced Liquid Processing System (ALPS) media are acceptable for dewatering.

3.2 Other polystyrene-based bead resins are acceptable for dewatering as long as the following conditions are met:

3.2.1 The resin shall have a moisture content ofless than or equal to 57% when shipped from the supplier to Seabrook Station.

3.2.2 Mixtures of resins shall have a weighted average of"as shipped" moisture contents less than or equal to 57%.

2 PCP Rev.01

3.3 In addition, all bead resins that qualify for dewatering shall also meet the following criteria:

3.3.1 Contain less than 1% oil or grease.

3.3.2 Significant quantities of organic contaminants that could inhibit dewatering capabilities will be excluded. Significant quantities are as defined in the dewatering instruction,

" Bead Resin / Activated Carbon Dewatering."

3.4 Physical degradation of the dewatered media shall be limited to that due to the dewatering process, resin transfer operations, and through normal use.

3.5 Cartridge process filters will be dried and disposed of as dry active waste (DAW). Filters that do not meet the exposure limits for DAW will be placed in High Integrity Containers (HICs) liners for disposal.

3.6 Waste containers shall meet the requirements of Reference 5.1.

4.0 ACCEPTANCE CRITERIA 4.1 All waste streams that undergo dewatering operations shall meet applicable acceptance criteria as defined in the appropriate Station Radwaste Department Instruction.

4.2 The Radwaste Department Supervisor shall determine if the radwaste instruction acceptance ,

criteria have been met.

4.3 The WSS shall determine if the following steps shall be performed after satisfying Acceptance Criteria 4.1 and 4.2. Wait at least eight hours before performing the following dewatering check:

4.3.1 Using the secondary dewatering line, less than one quart of water shall be obtained while dewatering the container for at least one hour.

4.3.2 If a secondary dewatering line is not available, the primary dewatering line shall be used to verify that less than one quad of water is obtained in at least one hour. When using the primary dewatering line for the final dewatering check, the installed suction gauge shall register less than 10" of Hg to ensure that filter blinding has not occurred. (See Reference 5.5.)

5.0 REFERENCES

5.1 CNSI Topical Report DW-11118-01-P-A, "CNSI Dewater Control Process Containers Topical Report."

5.2 CNSI Procedure FO-OP-023, " Bead Resin / Activated Carbon Dewatering Procedure for CNSI 14-215 or Smaller Liners."

5.3 CNSI Procedure FO-OP-025. " Dewatering Procedure for CNSI 24" Diameter Pressure Vessels, Rev. A. 5/22/87.

5.4 WN0958.51, " Bead Resin / Activated Carben Dewatering Procedure for CNSI 14-215 or Smaller Liners."

3 PCP Rev. 01

5.5 WN0958.60, "CNSI Work Instruction for Verification of no Free Standing Water in a Filter HIC at Seabrook Station."

5.6 RWO4, " Spent Filter Transfer Cask Operation" 5.7 Seabrook Station Health Physics StudyfrechnicalInformation Document 96-015 " Natural Drying Time Evaluation for Saturated Process Filters" September 1996.

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Appendix C Radioactive Liquid Effluent Monitoring Instrumentation Requirement Radioactive Liquid Efuuent Monitoring Instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.9.b. With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.9.b requires an explanation for the delay in correcting the inoperability in the next Annual Radiological Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Response

A review of the Action Statement Status tracking system for the period from January 1,1997 to December 31,1997 indicated Technical Specification 3.3.3.9 was entered for more than 30 consecutive days. Specifically, Liquid Radwaste Test Tank Flow Rate Measurement Device 1-WL-FIT-1458-1 was declared inoperable on April 20,1997 during a Waste Holdup Sump (WiiUS) discharge due to flow indication problems as WL-FIT-1458-1 failed high.1-WL-FIT-1458-1 was returned to operable status on August 1,1997.

During this time frame, a total 43 discharges were completed. The total actual discharge time duration was approximately 8.26 days. Technical Specification 3.3.3.9, Action b, Table 3.3-12, Item 2a, Action 31 was complied with during these discharges.

The following is a brief description of the outage time related to work completed on WL-FIT-1458-1:

Design Change DCR 96-022 installed vortex shedding dowmeter 1-WL-FIT-1458-1 which measures various treated effluent flows from the Waste Liquid (WL) and Steam Generator Blowdown (SB) systems before they are discharged to the environment. The previous magnetic flowmeter did not operate satisfactorily when discharging low conductivity treated water.

i The installation of the new vortex flowmeter was completed early in 1997 and after successful tests, was declared operable in April of 1997 and the DCR was closed out. Subsequent operation of this Howmeter before and during the fifth refueling outage was a mixed success. All process streams except the WHUS operated successfully. The WiiUS showed erratic readings during start of the WilUS batch operation and was declared inoperable on April 20,1997. Work Request 97W001115 and ACR 97-0760 were written by Control Room staff to correct the problem.

A meeting was held during the first week of May 1997 during which various test results were reviewed.

Subsequent Kepner-Tregoe analysis of the test results determined that only the WilUS batch did not perform satisfactorily and the cause was attributed to entrapped air in the WilUS stream. On May 15,1997 Work Request 97W001431 was written to implement Temporary Modification 97TMOD0018.

97TMOD0018 rotated the meter by 90 degrees. Testing in the reoriented configuration showed improved performance in all modes of operation including WilUS discharge. Ilowever, in the first week of July 1997 a new WHUS test showed erratic readings. This batch operation was subsequent to a strainer (SB-S-530) replacement upstream of the Dowmeter which involved draining the strainer chamber. The drained chamber introduced a bubble of air which caused erratic behavior of the

Radinactive Liould Efnuent Monitoring Instrumentation (continued) flowmeter. With the strainer chamber filled, subsequent tests conducted in the last week of July 1997 including a WilUS low flow test were successful and the installation was declared operable on August 1,1997 and the Technical Specification was exited.

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1 Appendix D

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Radioactive Gaseous Effluent Monitoring Instrumentation Recuirement: Radioactive Gaseous Effluent Monitoring Instrumentation Channels are required to be operable in accordance with Technical Specification 3.3.3.10.b. With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.10.b requires an explanation for the delay in correcting the inoperability in the next Annual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Reponst A review of the Action Statement Status tracking system for the period from January 1,1997 to December 31,1997 indicated Technical Specification 3.3.3.10 was not entered for more than 30 consecutive days. This includes outage time associated with 1-RM-RM-6505 (condenser offgas monitor), which is typically included in this check per Technical Clarification TS-056.

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Appendix E Liquid floidup Tanks Regmtsment Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.11.1.4, a description of the events leading to this condition is required in the next Annual Radiological Effluent Release Report in accordance with Technical Specification 3.11.1.4.

Resnonst No report required.

l l Apoendix F l R;idwaste Treatment Systems Requirement Technical Specification 6.14.1.a requires that licensee initiated changes to the Radwaste Treatment Systems (liquid, gaseous and solid) be submitted to the Commission in the Annual i

Radioactive Effluent Release Report for the period in which the change wes made. '

Response. No changes were made.

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Anoendix G Unplanned Releases Reguirement: Technical Specification 6.8.1.4 requires a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

Resoonse: No unplanned releases from the site to UNRESTRICTED AREAS were made in the period.

I Anoendix H Corrections To Prior Annual Radioactive Effluent Release Reports North Atlantic has identified the following corrections and/or clarifications to the below referenced Annual Radicactive Effluent Release Reports:

1996 Renort

1. North Atlantic submitted the 1996 Annual Radioactive Efiluent Release Report on April 30, 1997 via NYN-97036. Due to an administrative error, this submittal was inadvertently labeled NYN-96036 with a date of April 30,1996.

2. It was also identified that some infonnation contained in the report lacked the details required by Technical Specification 6.8.1.4b. The following provides the rationale in support of the chances made to the ODCM Table B.4-1 in Revision 16:

Air sample AP/CF-2 was renamed to "llarbor Road" from "llampton Marina"(sample designation). The name change to the sampler location was a result of the marina going into bankruptcy and closing down. The sampler was moved to an adjacent building (approximately 10-15 feet) to Seabrook Station's (Normandeau Associates) environmental field office. There is no change in the accuracy or reliability of the dose calculations or projections as this adjustment is still within the same meteorological sector and there are no impediments or interferences between the sampler and the plant.

Sediment Sample Point SE-07 aas defined as not being required for the REMP as defined in Part A of the ODCM. This change provided a clarification of the required sediment sample locations. There is no change to the accuracy or reliability of the dose calculations or projections from this adjustment.

Milk sample location TM-08 was redefined as TM-09. This was done as a clarification for the above referenced location. TM-08 was erroneously inserted into the ODCM from the

' Master Production File.' The milk sampling location actually used is TM-09 which is located 5.5 km from the Unit 1 Containment Building versus TM-08 which is located 4.3 km from the Unit 1 Containment Building. The Master Production File is presently controlled by North Atlantic. There is no change to the accuracy or reliability of the dose calculations or projection from this adjustment.

The location for TLD (monitor) TL-30 was redefined. The sample location was changed to more accurately define proper location designation of TL-30. Route 101C has been renamed to Route 27, this however, did not change the actual sample location for TL-30. There is no change to the accuracy or reliability of the dose calculations or projections from this adjustment.

Sample point SE-02 is a backup or add-on indicator station. This location is also at the discharge area. Technical Specifications require that the sediment indicator station be from the shoreline. This requirement is performed by SE-08. This change reflects a more accurate description of the road as the TLD is in the same location.

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Corrections to Prior Annual Radioactive Effluent Release Reports (continued)

The changes made by Revision 16 to the ODCM had been reviewed and found acceptable by the .

Station's SORC. The changes do not reduce the accuracy or reliability of dose calculations or setpoint determinations.

3. It was identified that the PCP changes described in the 1996 Annual Radioactive EfDuent Release Report required more explanation. Refer to Appendix B for additional detail.

1992/1995 Renorts Refer to Enclosure 3 for corrections to the 1992 and 1995 Annual Radioactive EfDuent Release Reports.

ENCLOSURE 2 TO NYN-98062

MEMORANDUM DE&S-BOLTON To W.121and - North Atlantic (SB 49-SS) Date March 12.1998 Group # REG 98-028 SBP 98-12 From T. A. Messier - Meteorologist W.O.# 004590000160000000 Subject SEABROOK 1997 METEOROLOGICAL DATA I.M.S.#

SUMMARIES FOR THE SEMIANNUAL File # shifdmemo.wnd RADIOACTIVE EFFLUENT RFI F ASE REPORT

REFERENCE:

1. DE&S Calculation No. SBC-849, "Seabrook Station Meteorological Data Joint Frequency Distributions: 1997".

DISCUSSION:

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Attached for submittal with the Seabrook Station Second Half 1997 Radioactive Effluent Release Report j (Tech Spec Item 6.8.1.4) are tables of joint frequency distributions of wind speed, wind direction, and atmospheric stability compiled from data collected by the Seabrook Primary Meteorological Monitoring j System (210-ft Met Tower) during 1997. The generation of these tables is documented in DE&S Calculation SBC-849 (Reference 1), a copy of which will be forwarded to the Seabrook Document Control Center.

Please do not hesitate to contact T. Messier (978-568-2378) if there are any questions. *

Attachments c: (w/o attachments) c: (w attachments) ;

L. Tardiff(SB 49-CH)

W.A. DiProfio (SB 49-SS)

J.M. Vargas (SB 01-62)

R.A. Marcello W.J. Merritt P.S. Littlefield R.B. Harvey M.S. Strum CMS Files 7dd[684MA/ / b Theodore A. Messier, Meteorologist Radiological Engineering Group I Environmental Health & Safety Department

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Peter S. Littlefdfd, Manager RadiologicarEngineering Group Environmental Health & Safety Department l

SEABROOK JAN97-DE097 MET DATA JOIPTT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 1,83 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW \1tBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 v 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .63 .00 .00 .00 .00 .00 .00 .00 .63 (2) .00 .C0 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 4-7 0 0 1 0 0 3 5 3 1 0 5 2 4 2 0 0 0 26 (1) .00 .00 .63 .00 .00 1.90 3.16 1.90 .63 .00 3.16 1.27 2.53 1.27 .00 .00 .00 16.46 (2) .00 .00 .01 .00 .00 .03 .06 .03 .01 .00 .06 .02 .05 .02 .00 .00 .00 .30 8-12 0 0 0 1 2 6 43 17 5 0 5 6 5 7 3 1 0 101 (1) .00 .00 .00 .63 1.27 3.80 27.22 10.76 3.16 .00 3.16 3.80 3.16 4 43 1.90 .63 .00 63.92 (2) .00 .00 .00 .01 .02 .07 .50 .20 .06 .00 .06 .07 .06 08 .03 .01 .00 1.17 13-18 0 0 0 1 0 0 6 1 0 2 3 5 3 h 3 0 0 29 (1) .00 .00 .00 .63 .00 .00 3.80 .63 .00 1.27 1.90 3.16 1.90 3.16 1. i .00 .00 18.35 (2) .00 .00 .00 .01 .00 .00 .07 .01 .00 .02 .03 .06 01 .06 .01 .00 .00 .34 19-24 0 0 0 0 0 0 0 0 0 0 0 0 s 1 0

0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .63 .00 .00 .00 .63 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .to .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 g oo .00 ALL SPEEDS 0 0 1 2 2 9 54 21 6 3 13 13 12 15 6 1 0 158 (1) .00 .00 .63 1.27 1.27 5.70 34.18 13.29 3.80 1.90 8.23 8.23 7.59 9.49 3.80 .63 .00 100.00 (2) .00 .00 .01 .02 .02 .10 .62 .24 .07 .03 .15 .15 .14 .17 w. 07 .01 .00 1.83 (1)*PTRCDft OF ALL COOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF A1.L GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL M .95 MPH) l I

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l SEABROOK JAN97-DEC97 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCEtn) = 2.54 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW fM NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1

, (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .45 .00 .00 .00 .45 l (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 4-7 0 0 1 0 2 1 14 3 2 0 0 3 0 5 4 1 0 36 (1) .00 .00 .45 .00 .91 .45 6.36 1.36 .91 .00 .00 1.36 .00 2.27 1.82 .45 .00 16.36 (2) .00 .00 .01 .00 .04 .01 .16 .03 .02 .00 .00 .03 .00 .06 .05 .01 .00 .42 8-12 0 0 0 4 12 10 19 7 3 4 4 24 13 18 7 3 0 128 (1) .00 .00 .00 1.82 5.45 4.55 8.64 3.18 1.36 1.82 1.82 10.91 5.91 8.18 3.18 1.3C .00 58.18 (2) .00 .00 .00 .05 .14 .12 .22 .08 .03 .05 .05 .28 .15 .21 .08 .w3 .00 1.48 13-18 0 0 0 1 0 0 0 0 0 1 5 4 4 15 17 1 0 48 (1) .00 .00 .00 .45 .00 .00 .00 .00 .00 .45 2.27 1.82 1.82 6.82 7.73 .45 .00 21.82 (2) .00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .06 .05 .05 .17 .20 .01 .00 .55 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ? ? O O 7 .

(1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.18 .00 .00 3.18 '

(2) .00 .00 .00 .00 .00 .00 .00 .r. .00 .00 .00 .00 .00 .00 .'0 8 .00 .00 .08 GT 24 0 0 0 0 0 0 0 u 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ;00 .00 ALL SPEEDS 0 0 1 5 14 11 33 10 5 5 9 31 17 39 35 5 0 'O (1) .00 .00 .45 2.27 6.36 5.00 15.00 4.55 2.27 2.27 4.09 14.09 7.73 17.73 15.91 2.27 .00 100. 0 (2) .00 .00 .01 .06 .16 .13 .38 .12 .06 .06 .10 .36 .20 .45 ". 4 0 .06 .00 2.54 (1)= PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)sPERCDn OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Cs CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) l l

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l SEABROOK JAN97-DEC97 HET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT 'IM'ER) 43.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCDfT) = 4.65 WIND DIRECTION FROM SPEED N NNE NE ENE E E?E SE SSE 5 SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .0G .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 1 1 1 0 1 0 0 0 0 1 1 0 0 1 0 7 (1) .00 .00 .25 .25 .25 .00 .25 .00 .00 .00 .00 .25 .25 .00 .00 .25 .00 1.74 (2) .00 .00 .01 .01 .01 .00 .01 .00 .00 .00 .00 .01 .01 .00 .00 .01 .00 .08 4-7 1 0 1 2 11 3 11 8 2 3 3 3 5 13 8 3 0 77 (1) .25 .00 .25 .50 2.74 .75 2.74 1.99 .50 .75 .75 .75 1.24 3.23 1.99 .75 .00 19.15 (2) .01 .00 .01 .02 .13 .03 .13 .09 .02 .03 .03 .03 .06 .15 .09 .03 .00 .89 8-12 1 2 1 16 26 14 25 6 1 1 16 21 25 29 20 3 0 207 (1) .25 .50 .25 3.98 6.47 3.48 6.22 1.49 .25 .25 3.98 5.22 6.22 7.21 4.98 .75 .00 51.49 (2) .01 .02 .01 .18 .30 .16 .29 .07 .01 .01 .18 .24 .29 .34 .23 .03 .00 2.39 13-18 0 0 1 4 1 0 1 0 0 2 4 1 4 43 39 3 0 103 (1) .00 .00 .25 1.00 .25 .00 .25 .00 .00 .50 1.00 .25 1.00 10.70 9.70 .75 .00 25.62 (2) .00 .00 .01 .05 .01 .00 .01 .00 .00 .02 .05 .01 .05 .50 .45 .03 .00 1.19 19-24 0 0 0 0 0 0 0 0 0 0 1 0 0 2 5 0 0 8 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .25 .00 .00 .50 1.24 .00 .00 1.99 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .06 .00 .00- .09 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 400 .00 j ALL SPEEDS 2 2 4 23 39 17 38 14 3 6 24 26 35 87 72 10 0 402 (1) .50 .50 1.00 5.72 9.70 4.23 9.45 3.48 .75 1,49 5.97 6.47 8.71 21.64 17.91 2.49 .00 100.00 (2) .02 .02 .05 .27 .45 .20 .44 .16 .03 .07 .28 .30 .40 1.01 ". 8 3 .12 .00 4.65 (1)sPERCEPTI' OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL OOOD OBSERVATIONS FOR THIS PERIOD C8 CALM (WIND SPEED LESS THAN OR EQUAL 1V .95 MPH) j i

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SEABROOK JAN97-DEC97 MET DATA JOIt3 FREQUENCY DISTRIBUTION (210-FOOT 70WER) 43.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) . 45.36 WIND D.IRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW fM NrW VRBL TOTAL MPH CALM 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 (2) .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 C-3 7 7 15 3 7 5 6 8 12 17 17 13 24 26 35 23 0 225 (1) .18 .18 .38 .08 .18 .13 .15 .20 .31 .43 .43 .33 .61 .66 .89 .59 .00 5.73 (2) .08 .08 .17 .03 .08 .06 .07 .09 .14 .20 .20 .15 .28 .30 .40 .27 .00 2.60 4-7 93 41 61 61 93 41 82 79 69 61 59 97 131 160 140 117 0 1385 (1) 2.37 1.04 1,55 1.55 2.37 1.04 2.09 2.01 1.76 1.55 1.50 2.47 3.34 4,08 3.57 2.98 .00 35.29 (2) 1.07 .47 .70 .70 1.07 .47 .95 .91 .80 70 .68 1.12 1.51 1.85 1.62 1.35 .00 16.01 8-12 58 42 98 86 82 66 56 50 39 49 118 145 159 276 197 54 0 1575 (1) 1.48 1.07 2.50 2.19 2.09 1.68 1.43 1.27 .99 1.25 3.01 3.69 4.05 7.03 5.02 1.38 .00 40.13 (2) .67 .49 1.13 .99 .95 . 7 f- .65 .58 .45 .57 1.36 1.68 1.84 3.19 2.28 .62 .00 18.20 13-18 7 8 44 23 20 4 2 3 8 5 39 31 75 171 155 9 0 604 (1) .18 .20 1.12 .59 .51 .10 .05 .08 .20 .13 .99 .79 1.91 4.36 3.95 .23 .00 15.39 (2) .08 .09 .51 .27 .23 05 .02 .03 .09 .06 .45 .36 .87 1.98 1,79 .10 .00 6.98 19-24 1 0 22 0 4 4 0 0 0 1 7 0 5 41 26 ' 2 0 113 (1) .03 .00 .56 .00 .10 .10 .00 .00 .00 .03 .18 .00 .23 1.04 .66 .05 .00 2.88 (2) .01 .00 .25 .00 .05 .05 .00 .00 .00 .01 .08 .00 .06 .47 .'3 0 .02 .00 1.31 GT 24 0 0 10 0 3 0 0 0 0 0 0 0 0 7 2 0 0 22 (1) .00 .00 .25 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .18 .05 .00 .00 .56 (2) .00 .00 .12 .00 .03 .00 .00 .00 .00 .00 .00 .00 .00 .08 .02 .00 ;00 .25 ALL SPEEDS 166 98 250 173 209 120 147 140 128 133 240 286 394 681 555 205 0 3925 (1) 4.23 2.50 6.37 4.41 5.32 3.06 3.75 3.57 3.26 3.39 6.11 7.29 10.04 17.35 14.14 5.22 .00 100.00 (2) 1.92 1.13 2.89 2.00 2.42 1.39 1.70 1.62 1.48 1.54 2.77 3.31 4.55 7.87 f.41 2.37 .00 45.36 (11=PERCDff OF ALL GOOD OBSERVATIONS 70R THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN O.t EQUAL 'IV .95 MPH) 1 i

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SEABROOK JAN97-CEC 97 MET DATA JOINT FRIQUDICY DISTRIBUTION (210-FOOT TOhTR) 43.0 FT WIND DATA STABILITY CLASS E CLASS FREQUDICY (PERCENT) e 31.17 WIND DIRECTION FROM SPEED N 22.'E NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM 2 2 0 1 0 0 2 1 0 0 2 0 0 0 0 0 0 10 (1) .07 .07 .00 .04 .00 .00 .07 .04 .00 .00 .07 .00 .00 .00 .00 .00 .00 .37 (2) .02 .02 .00 .01 .00 .00 .02 .01 .00 .00 .02 .00 .00 .00 .00 .00 .00 .12 C-3 16 20 19 17 26 8 14 18 19 32 35 32 58 44 40 33 0 431 (1) .59 .74 .70 .63 .96 .30 .52 .67 .70 1.19 1.30 1.19 2.15 1.63 1.48 1.22 .00 15.98 (2) .38 .23 .22 .20 .30 .09 .16 .21 .22 .37 .40 .37 .67 .51 .46 .38 .00 4.98 4-7 36 24 33 34 41 35 61 59 49 99 114 249 244 183 132 62 0 1455 (1) 1.33 .89 1.22 1.26 1.52 1.30 2.26 2.19 1,82 3.67 4.23 9.23 9.05 6.79 4.89 2.30 .00 53.95 (2) .42 .28 .38 .39 .47 .40 .70 .68 .57 1.14 1.32 2.88 2.82 2.11 1.53 .72 .00 16.81 8-12 11 5 12 7 13 15 17 19 16 37 114 163 66 111 63 5 0 674 (1) .41 .19 .44 .26 .48 .56 .63 .70 .59 1.37 4.23 6.04 2.45 4.12 2.34 .19 .00 24.99 (2) .13 .06 .14 .08 .15 .17 .20 .22 .18 .43 1.32 1.88 .76 1.28 .73 .06 .00 7.79 13-18 5 3 5 1 12 6 1 4 3 2 24 16 6 9 6 3 0 106 (1) .19 .11 .19 .04 .44 .22 .04 .15 .11 .07 .89 .59 .22 .33 .22 .11 .00 3.93 (2) .06 .03 .06 .01 .14 .07 .01 .05 .03 .02 .28 .18 .07 .10 .07 .03 .00 1.23 19-24 0 0 3 0 9 2 0 0 0 0 0 1 0 0 0 O O 15 (1) .00 .00 .11 .00 .33 .07 .00 .00 .00 .00 .00 .04 .00 .00 .00 .00 .00 .56 (2) .00 .00 .03 .00 .10 .02 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .17 CT 24 0 0 3 0 3 0 0 0 0 0 0 0 0 0 0 0 0 6 (1) ,00 .00 .11 .00 .11 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .22 (2) .00 .00 .03 .00 .03 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4 00 .07 ALL SPEEDS 70 54 75 60 104 66 95 101 87 170 289 461 374 347 241 103 0 2697 (1) 2.60 2.00 2.78 2.22 3.86 2.45 3.52 3.74 3.23 6.30 10.72 17.09 13.87 12.87 8.94 3.82 .00 100.00 (2) .81 .62 .87 .69 1.20 .76 1.10 1.17 1.01 1.96 3.34 5.33 4.32 4.01 7.79 1.19 .00 31.17 (1)*PERCDIT OF ALL GOCD OBSERVATIONS FOR THIS PAOE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOK JAN97-DEC97 MET DATA Jolte FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WI!D DATA STABILITY CLASS F CLASS FREQUENCY (PERCDft) = 7.65 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CAIJt 2 0 0 0 0 0 0 0 1 0 0 1 0 1 0 0 0 5 (1) .30 .00 .00 .00 .00 .00 .00 .00 .15 .00 .00 .15 .00 .15 .00 .00 .00 .76 (2) .02 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 .00 .01 .00 .00 .00 .06 C-3 6 5 10 1 11 6 5 4 4 13 29 39 54 75 42 15 0 325 i (1) .91 .76 1.51 1.06 1.66 .91 .76 .60 .60 1.96 4.38 5.89 8.16 11.33 6.34 2.27 .00 49.09 l (2) .07 .06 .22 .00 .13 .07 .06 .05 .05 .15 .34 .45 .62 .87 .49 .17 .00 3.76

-7 1 0 2 1 8 0 2 3 4 7 28 64 73 60 55 19 0 327 l

(1) .15 .00 .30 .15 1.21 .00 .30 .45 .60 1.06 4.23 9.67 11.03 9.06 8.31 2.87 .00 49.40 (2) .01 .00 .02 .01 .09 .00 .02 .03 .05 .08 .32 .74 .84 .69 .64 .22 .00 3.78 8-12 0 0 0 0 0 0 0 0 0 0 0 4 1 0 0 0 0 5 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .60 .15 .00 .00 .60 .00 .76 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .01 .00 .00 .00 .00 .06 l 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0' 0 0 0 l (1) .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .,0 0 .00 .00 .00 l l (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '

CT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 400 .00 ALL SPEEI.1 9 5 12 8 19 6 7 7 9 20 57 108 128 136 97 34 0 662 (1) 1.36 .76 1.81 1.21 2.87 .91 1.06 1.06 1.36 3.02 8.61 16.31 19.34 20.54 14.65 5.14 .00 100.00 (2) .10 .06 .14 .09 .22 .07 .08 .08 .10 .23 .66 1.25 1.48 1.57 1*.12 .39 .00 7.65 (1) =PERCD.'T OF ALL COOD OBSERVATIONS FOR THIS PAGE (2)=PERCDR OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

SEABROOK JAN97-DEC97 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT WIND DATA STABILITY CLASS O CLASS FREQUENCY ( PERCD1T) = 6.81 WIND DIRECTION FROM l

SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W MM NW NNW VRBL TOTAL MPH '

CALM 0 3 1 0 0 0 0 0 0 0 0 0 3 0 0 0 0 7 l (1) .00 .51 .17 00 .00 .00 .00 .00 .00 .00 .00 .00 .51 .00 .00 .00 .00 1.19 (2) .00 .03 .01 .00 00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .00 .08 ;i C-3 0 l

2 3 2 9 2 0 4 0 3 18 88 104 116 36 10 0 397 i ill .34 .51 .34 1,53 .34 .00 .00 .68 .00 .51 3.06 14.94 17.66 19.69 6.11 1.70 .00 67.40 (23 .02 .03 .C2 .10 .02 .00 .00 .05 .00 .03 .21 1.02 1.20 1.34 .42 .12 .00 4.59 4-7 0 0 0 2 5 0 0 0 0 3 7 33 32 58 38 6 0 184 (1) .00 .00 .00 .34 .85 .00 .00 .00 .00 .51 1.19 5.60 5.C3 9.85 6.45 1.02 .00 31.24 (2) .00 .00 .00 .02 .06 .00 .00 .00 .00 .03 .08 .38 .37 .67 .44 .07 .00 2.13 8-12 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .17 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .17 (2) .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l

.01 13-16 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

-( 1 ) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0' O O O (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .,0 0 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 400 .00 ALL SPEEDS 2 6 3 11 7 1 0 4 0 6 25 121 139 174 74 16 0 589 (1) .34 1.02 .51 1.87 1.19 .17 .00 .68 .00 1.02 4.24 20.54 23.60 29.54 12.56 2.72 .00 100.00 (2) .02 .07 .03 .13 .08 .01 .00 .05 .00 .07 .29 1.40 1.61 2.01 F. 8 6 .18 .00 6.81 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) =PERCDt? OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

SEABROOK JAN97-DEC97 MET DATA JOIrrr FREQUENCY DISTRIBUTION (210-FOOT TOWER) 43.0 FT wn2D DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED N NME NE ENE E ESE SE SSE S SSW SW WSW W WNW NW PRM W" TOTAL MPH CALM 4 5 1 1 0 0 3 1 1 0 2 1 3 1 0 0 0 23 (1) .05 .06 .01 .01 .00 .00 .03 .01 .01 .00 .02 .01 .03 .01 .00 .00 .00 .27 (2) .05 .06 .01 .01 .00 .00 .03 .01 .01 .00 .01 .01 .03 .01 .00 .00 .00 .27 C-3 31 35 47 37 47 19 26 34 35 66 99 173 241 262 153 82 0 1387 (1) .36 .40 .54 .43 .54 .22 .30 .39 .40 .76 1.14 2.00 2.79 3.03 1.77 .95 .00 16.03 (2) .36 .40 .54 .43 .54 .22 .30 .39 .40 76 1.14 2.00 2.79 3.03 1.77 .95 .00 16.03 4-7 131 65 99 100 160 83 175 155 127 173 216 451 489 481 377 208 0 3490 (1) 1.51 .75 1.14 1.16 1.85 .96 2.02 1,79 1.47 2.00 2.50 5.21 5.65 5.56 4.36 2.40 .00 40.33 (2) 1.51 .75 1.14 1.16 1.85 .96 2.02 1.79 1.47 2.00 2.50 5.21 5.65 5.56 4.36 2.40 .00 40.33 f

8-12 70 49 111 114 135 112 160 99 64 91 257 363 269 441 290 66 0 2691 l (1) .81 .57 1.28 1.32 1.56 1.29 1.85 1.14 .74 1.05 2.97 4.20 3.11 5.10 3.35 76 .00 31.10 (2) .81 .57 1.28 1.32 1.56 1.29 1.85 1.14 74 1.05 2.97 4.20 3.11 5.10 3.35 .76 .00 31.10 13-18 12 11 50 30 33 10 10 8 il 12 75 57 92 243 220 16 0 890 (1) .14 .13 .58 .35 .38 .12 .12 .09 .13 .14 .87 .66 1.06 2.81 2.54 .18 .00 10.29 (2) .14 .13 .58 .35 .38 .12 .12 .09 .13 .14 .87 .66 1.06 2.81 2.54 .18 .00 10.29 e

19-24 1 0 25 0 13 6 0 0 0 1 8 1 5 44 38 2 0 144 (1) .01 .00 .29 .00 .15 .07 .00 .00 .00 .01 .09 .01 .06 .51 A4 .02 .00 1.66 (2) .01 .00 .29 .00 .15 .07 .00 .00 .00 .01 .09 .01 .06 .51 .44 .02 .00 1.66 GT 24 0 0 13 0 6 0 0 0 0 0 0 0 0 7 2 0 0 28 (1) .00 .00 .15 .00 .07 .00 .00 .00 .00 .00 .00 .00 .00 .08 .02 .00 ,00 .32 (2) .00 .00 .15 .00 .07 .00 .00 .00 .00 .00 .00 .00 .00 .08 .02 ,00 *00

. .32 ALL SPEEDS 249 165 346 282 394 230 374 297 238 343 657 1046 1099 1479 1080 374 0 8653 (1) 2.88 1.91 4.00 3.26 4.55 2.66 4.32 3.43 2.75 3.96 7.59 12.09 12.70 17.09 11,48 4.32 .00 100.00 (2) 2.88 1.91 4.00 3.26 4.55 2.66 4.32 3.43 2.75 3.96 7.59 12.09 12.70 17.09 12.48 4.32 .00 100.00 (llePERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)* PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

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SEABROOK JAN97-DE097 MET DATA JOINT FREQUENOY DISTRIBUTION (210-FOOT TOWER)

' 09.0 FT WIND DATA

. STABILITY CLASS A CLASS FREQUENCY ( PERCDIT) = 1.82 WIND DIRECTION FROM SPEED N tale t.'E ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 0-3 0 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .63 .63 .00 .00 .00 .00 .00 .00 .00 .00 1.27 (2) .00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .02 4-7 0 0 0 0 0 2 1 1 0 1 3 2 3 1 0 0 0 14 (1) .00 .00 .00 .00 .00 1.27 .63 .63 .00 .63 1.90 1.27 1.90 .63 .00 .00 .00 8.86 (2) .00 .00 .00 .00 00 .02 .01 .01 .00 .01 .03 .02 .03 .01 .00 .00 .00 .16 8-12 0 1 0 0 2 3 21 7 3 0 2 6 3 1 0 0 0 49 (1) .00 .63 .00 .00 1.27 1.90 13.29 4.43 1.90 .00 1.27 3.80 1.90 .63 .00 .00 .00 31.01 (2) .00 .01 .00 .00 .02 .03 .24 .08 .03 .00 .02 .07 .03 .01 .00 .00 .00 .56 13-18 0 0 0 2 0 1 25 16 3 0 3 1 7 10 3 1 0 72 (1) .00 .00 .00 1.27 .00 .63 15.82 10.13 1.90 00 1.90 .63 4.43 6.33 1.90 .63 .00 45.57 (2) .00 .00 .00 .02 .00 .01 .29 .18 .03 .00 .03 .01 .08 .11 .03 .01 .00 .83 19-24 0 0 0 0 0 0 2 3 0 2 3 4 0 3 13 0 0 18 (1) .00 .00 .00 .00 .00 .00 1.27 1.90 .00 1.27 1.90 2.53 .00 1.90 .63 .00 .00 11.39 (2) .00 .00 .00 .00 .00 .00 .02 .03 .00 .02 .03 .05 .00 .03 .01 .00 .00 .21 07 24 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 0 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .63 1.27 .00 .00 .00 1.90 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .02 .00 .00 400 .03 ALL SPEEDS 0 1 0 2 2 6 49 28 7 3 11 13 14 17 4 1 0 158 (1) .00 .63 .00 1.27 1.27 3.80 31.01 17.72 4.43 1.90 6.96 8.23 8.86 10.76 2.53 .63 .00 100.00 (2) .00 .01 .00 .02 .02 .07 .56 .32 .08 .03 .13 .15 .16 .20

05

. .01 .00 1.82 (1)=PERODIT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) =PERCDIT OF AIL GOOD OBSERVATIONS FOR THIS PERIOD Ce CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)

SEABROOK JAN97-DEC97 MET DATA JOItfr FREQUDICY DISTRIEUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = 2.53 WIND DIRECTION FROM SPEED N ht'E NE ENE E ESE SE SSE S SSW SW WSW W MM tM t@M VRBI. TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4-7 0 0 1 0 1 1 3 1 0 0 1 0 0 1 3 0 0 12 (1) .00 .00 .45 .00 .45 .45 1.36 .45 .00 .00 .45 .00 .00 .45 1.36 .00 .00 5.45 (2) .00 .00 .01 .00 .01 .01 .03 ,01 .00 .00 .01 .00 .00 .01 .03 .00 .00 .14 8-12 0 0 0 2 13 9 16 9 2 3 0 11 2 11 2 1 0 91 (1) .00 .00 .00 .91 5.91 4.09 7.27 4.09 .91 1.36 .00 5.00 .91 5.00 .91 .45 .00 36.82 (2) .00 .00 .00 .02 .25 .10 .18 .10 .02 .03 .00 .13 .02 .13 .02 .01 .00 .93 13-18 0 0 1 2 1 0 8 6 1 1 5 18 12 14 10 5 0 84 (1) .00 .00 .45 .91 .45 .00 3.64 2.73 .45 .45 2.27 8.18 5.45 6.36 4.55 2.27 .00 38.18 (2) .00 .00 .01 .02 .01 .00 .09 .07 .01 .01 .06 .21 .14 .16 .11 .06 .00 .97 e

19-24 0 0 0 0 0 0 0 1 0 1 2 4 4 14 11 0 0 37 (1) .00 .00 .00 .00 .00 .00 .00 .45 .00 .45 .91 1.82 1.82 6.36 5.t o .00 .00 16.82 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 .02 .05 .05 .16 .13 .00 .00 .43 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 5 0 0 6 l (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .45 2.27 .00 00 2.73 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .06 .00 *00

. .07 ALL SPEEDS 0 0 2 4 15 to 27 17 3 5 8 33 18 41 31 6 0 220 (1) .00 .00 .91 1.82 6.82 4.55 12.27 7.73 1.36 2.27 3.64 15.00 8.18 18.64 14,09 2.73 .00 100.00 (2) .00 .00 .02 .05 .37 .11 .31 .20 .03 .06 .09 .38 .21 .47 .36 .07 .00 2.53 (1) PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) =PERCDFF OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 1

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l SEABROOK JAN97-DEC97 MET DATA JOItrf FREQUENCY DISTRIBUTION (210-FOOT 1tWER) 209.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCCIT) = 4.62 WIND DIRECTION FROM SPEED N NNE NE DIE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 2 0 0 1 0 1 0 0 0 0 0 0 0 0 0 0 4 (1) .00 .50 .00 .00 .25 .00 .25 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1.00 (2) .00 .02 .00 .00 .01 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 4-7 2 0 0 1 6 5 3 3 0 2 2 3 3 8 5 2 0 45 (1) .50 .00 .00 .25 1.49 1.24 .75 .75 .00 .50 .50 .75 .75 1.99 1.24 .50 .00 11.19 (2) .02 .00 .00 .01 .07 .06 .03 .03 .00 .02 .02 .03 .03 .09 .06 .02 .00 .52 8-12 1 4 1 11 15 18 18 8 2 1 7 7 13 16 8 2 0 132 (1) .25 1.00 .25 2.74 3.73 4.48 4.48 1.99 .50 .25 1.74 1.74 3.23 3.98 1.99 .50 .00 32.84 (2) ,01 .05 .01 .13 .17 .21 .21 .09 .02 .01 .08 .08 .15 .18 .09 .02 .00 1.52 13-18 0 0 2 10 3 1 5 13 3 1 9 17 16 41 39 2 0 162 (1) .00 .00 .50 2.49 .75 .25 1.24 3.23 .75 .25 2.24 4.23 3.98 10.20 9.70 .50 .00 40.30 (2) .00 .00 .02 .11 .03 .01 .06 .15 .03 .01 .10 .20 .18 .47 .45 .02 .00 1.86 19-24 1 0 0 1 0 0 0 2 0 1 3 1 5 24 12 0 0 50 i (1) .25 .00 .00 .25 .00 .00 .00 .50 .00 .25 .75 .25 1.24 5.97 2.1P 9 .00 .00 12.44 I (2) .01 .00 .00 .01 .00 .00 .00 .02 .00 .01 .03 .01 .06 .28 .14 .00 .00 .57 OT 24 0 0 0 0 0 0 0 0 0 0 1 0 0 4 4 0 0 9 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .25 .00 .00 1.00 1.00 .00 .00 2.24 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .05 .05 .00 *00

. .10 ALL SPEEDS 4 6 3 23 25 24 27 26 5 5 22 28 37 93 68 6 0 402 (1) 1.00 1.49 .75 5.72 6.22 5.97 6.72 6.47 1.24 1.24 5.47 6.97 9.20 23.13 1L92 1.49 .00 100.00 (2) .05 .07 .03 .26 .29 .28 .31 .30 .06 .06 .25 .32 .43 1.07 .78 .07 .00 4.62 (1)*PERCDTP OF ALL OOOD OBSERVATIONS FOR THIS PAGE (2)=PERCD1T OF ALL GOOD CBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 1 l

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SEABROOK JAN97-DEC97 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY C1 ASS D CLASS FREQUENCY (PERCENT) = 45.15 WIND DIRECTION FROM SPEED N NNE NE E22E E ESE SE SSE S SSW SW WSW W WtM NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .00 .00 .03 .00 .00 .05 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 ,00 .00 .02 C-3 10 4 7 9 7 7 7 7 2 6 7 7 5 7 12 8 0 112 (1) .25 .10 ,18 .23 .18 .18 .18 .18 .05 .15 .18 .18 .13 .18 .31 .20 .00 2.85 (2) .11 .05 .08 .10 .08 .08 .08 .08 .02 .07 .08 .08 .06 .08 .14 .09 .00 1.29 4-7 57 26 33 34 43 43 44 35 25 33 39 30 48 62 64 59 0 675 (1) 1.45 .66 .84 .87 1.09 1.09 1.12 .89 .64 .84 .99 .76 1.22 1.58 1.63 1.50 .00 17.18 (2) .66 .30 .38 .39 .42 .49 .51 .40 .29 .38 .a. .34 .55 .71 .74 .68 .00 7.76 8-12 93 54 73 76 50 62 84 71 67 49 d8 115 118 183 137 87 0 1407 (1) 2.37 1.37 1.86 1.93 1.27 1.58 2.14 1.81 1.71 1.25 24 2.93 3.00 4.66 3.49 2.21 .00 35.82 (2) 1.07 .62 .84 .87 .57 .71 .97 .82 .77 .56 01 1.32 1.36 2.10 1.57 1.00 .00 16.17 i I

13-18 46 52 71 21 29 16 20 38 18 31 76 89 111 227 181 34 0 1098 (1) 1.17 1.32 1.81 .53 .74 .41 .71 .97 .'s. .79 2 44 2.27 2.83 5.78 4.61 .87 .00 27.95 (2) .53 .60 .82 .24 .33 .18 32 .44 .32 .36 1.10 1.02 1.28 2.61 2.08 .39 .00 12.62 19-24 11 13 29 2 6 3 6 2 7 1 24 16 66 163 87 4 0 440 (1) .28 .33 .74 .05 .15 .08 .15 .05 .18 .03 .61 .41 1.C8 4.15 2.01 .10 .00 11.20 (2) .13 .15 .33 .02 .07 .03 .07 .02 .08 .01 .28 18 .76 1.87 1.00 .05 .00 5.06 GT 24 5 7 29 2 8 5 0 0 0 2 11 4 22 74 20 5 0 194 (1) .13 .18 .74 .05 .20 .13 .00 .00 .00 .05 .28 .10 .56 1.88 .51 .13 ,00 4.94 (2) .06 .08 .33 .02 .09 .06 .00 .00 .00 .02 .13 .05 .25 .85 23 .06 6.00 2.23 ALL SPEEDS 222 156 242 144 143 136 169 153 129 122 266 261 370 716 502 197 0 3928 (1) 5.65 3.97 6.16 3.67 3.64 3.46 4.30 3.90 3.28 3.11 6.77 6.64 9.42 18.23 11 7B 5.02 .00 100.00 1 (2) 2.55 1.79 2.78 1.66 1.64 1.56 1.94 1.76 1.48 1.40 3.06 3.00 4.25 8.23 5.77 2.26 .00 45.15 '

(1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PACE (21sPERCENI' OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Co CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) l 1

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SEAEROOK JAN97 CEO97 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT)

31.24 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW t#M "RBL TOTAL MFH CALM 1 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 2 (1) .04 .00 .00 .00 .00 .04 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .07 (2) .01 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 l

C-3 6 10 9 10 3 10 6 9 5 9 8 6 4 2 3 5 0 105 (1) .22 .37 .33 .37 .11 .37 .22 .33 .18 .33 .29 .22 .15 .07 .11 .18 .00 3.86 (2) .07 .11 .10 .11 .03 .11 .07 .10 .06 .10 .09 .07 .05 .02 .03 .06 .00 1.21 4-7 25 la 31 15 23 23 38 25 24 22 31 18 19 27 27 23 0 391 (1) .92 .74 1.14 .55 .85 .85 1,40 .92 .88 .81 1.14 .66 .70 .99 .99 .85 .00 14.39 (2) .29 .23 .36 .17 .26 .26 .44 .29 .28 .25 .36 .21 .22 .31 .31 .26 .00 4.49 8 12 44 36 21 18 10 21 44 56 55 86 112 124 107 161 114 57 0 1066

11) 1.62 1,32 >77 .66 .37 .77 1.62 2.06 2.02 3.16 4.12 4.56 3.94 5.92 4.19 2.10 .00 39.22

12) .51 .41 .24 .21 .11 .24 .51 .64 ,63 ,99 1.29 1.43 1.23 1.85 1.31 .66 .00 12.25 13-18 22 13 13 6 7 10 18 21 24 53 135 20s 172 167 103 19 0 991 (1) .81 .48 48 .22 .26 .37 .66 .77 .88 1.95 4.97 7.65 6.33 6.14 3.79 .70 .00 36.46 (2) .25 .15 .15 ,07 .06 .11 .21 .24 .28 ,61 1.55 2.39 1.98 1.92 1.18 .22 .00 11.39 19-24 4 5 4 1 9 to 1 2 6 2 25 22 7 15 9 4 0 126 (1) .15 .18 .15 .04 .33 .37 .04 .07 .22 .07 .92 .81 ,26 .55 .33 .15 .00 4.64 (2) .05 .06 .05 .01 .10 .11 .01 .02 .07 .02 .29 .25 .08 .17 .10 .05 .00 1.45 CT 24 2 1 7 1 14 3 1 1 0 0 2 0 3 2 0 0 0 37 1 (1) .07 .04 .26 .04 .52 .11 .04 .04 .00 .00 .07 .00 .11 .07 .00 .00 ,00 1.36 I (2) .02 .01 .08 .01 .16 .03 .01 .01 .00 .00 .02 .00 .03 .00 .00 .00 *00

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ALL SPEEDS 104 85 85 51 66 79 108 114 114 172 313 378 312 374 256 108 0 2718 l (1) .i . 8 ) 3.13 3.13 1.88 2.43 2.87 3.97 4.19 4.19 6.33 11.52 13.91 11.48 13.76 1,42 3.97 .00 100.00 (2) 1.20 .98 .98 .59 76 .90 1.24 1.31 1.31 1.98 3.60 4.34 3.59 4.30 2.94 1.24 .00 31.24 l (1)=PEROENT OF ALL 000D OBSERVATIONS FOR THIS PAGE (2)sPERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) i I

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SEADROOK JAN97-0E097 MET DATA JODTP FREQUENCY DIS'!?.1BUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY CLASS T CLASS FREQUENCY (PERCENT) = 7.78 W.ND DIRECTION FROM SPEED N ta:E NE ENE E ESE F4 SSE S SSW SW WSW W WNW NW PDM VRBL TOTAL i MPH '

CALM 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 C 0 1 (1) .00 .00 .00 .00 .00 .15 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .15 I (2) .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 l C-3 2 2 4 2 5 5 4 4 4 4 1 2 3 1 2 1 0 46 l (1) .30 .30 .59 .30 .74 .74 .59 .59 .59 .59 .15 .30 .44 .15 .30 .15 .00 6.79 i (2) .02 .02 .05 .02 .06 .06 .05 .05 .05 .05 .01 .02 .03 .01 .02 .01 .00 .53 1

4-7 14 10 5 8 5 7 6 4 12 9 17 10 13 13 7 7 0 147 (1) 2.07 1.48 .74 1.18 .74 1.03 .89 .59 1.77 1.33 2.51 1.48 1.92 1.92 1.03 1.03 .00 21.71 (2) .16 11 .06 .09 .06 .08 .07 .05 .14 .10 .20 .11 .15 .15 .08 .08 .00 1.69 8-12 27 10 2 4 4 2 2 8 17 18 24 22 51 59 47 26 0 325 (1) 3.99 1.48 .30 .59 .59 .30 .30 1.19 2.51 2.66 3.55 3.25 7.53 8.71 6.94 4.14 .00 48.01 (2) .31 .11 .02 .05 .05 .02 .02 .09 .20 .21 .28 .25 .59 .68 .54 .32 .00 3.74 i 13-18 3 3 0 0 1 0 0 0 1 1 15 31 29 36 25 13 0 158 (1) .44 .44 .00 .00 .15 .00 .00 .00 .15 .15 2.22 4.58 4.28 5.32 3.69 1.92 .00 23.34 (2) .03 .03 .00 .00 .01 .00 .00 .00 .01 .01 .17 .36 .33 .41 .29 .15 .00 1.82 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .20 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 OT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,00 .00 .00 $00 .00 ALL SPEEDS 46 25 11 14 15 15 12 16 34 32 57 65 96 109 81 49 0 677 (1) 6.79 3.69 1.62 2.07 2.22 2.22 1,77 2.36 5.02 4.73 8.42 9.60 14.18 16.10 1(.96 7.24 .00 100.00 (2) .53 .29 .13 .16 .17 .27 .14 .18 .39 .37 .66 .75 1.10 1.25 .93 .56 .00 7.78 (1)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (21= PERCENT OF ALL GOCD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 4

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i SEABROOK JA0:37-OE!97 MET DATA JOINT FRE2CDiCY DISTRIBUTION (210-FOOT TOWER) )

l 209.0 FT WIIC ::ATA STABILITY CLASS G CLASS FREQUENCY (PERCDIT) = 6.86 l WI!C DIRECTION FROM EPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL MPH CALM C 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0 0 2 (1) .00 .00 .00 .00 .00 .17 .17 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .34 (2) .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 C-3 4 2 5 5 3 4 7 5 2 2 2 1 5 3 5 3 0 58 (1) .67 .34 .84 .84 .50 .67 1.17 .84 .34 .34 .34 .17 .84 .50 .84 .50 .00 0 72 (2) .05 .02 .06 .06 .03 .05 .09 .06 .02 .02 .02 .01 .06 .03 .06 .03 .00 .67 4-7 15 7 9 2 4 0 5 8 8 8 19 25 22 15 15 11 0 173 (1) 2.51 1.17 1.51 .34 .67 .00 .84 1.34 1.34 1.34 3.18 4.19 3.69 2.51 2.51 1.84 .00 28.98 (2) 17 .08 .10 .02 .05 .00 .06 .09 .09 .09 .22 .29 .25 .17 .17 .13 .00 1.99 8-12 25 8 3 2 0 0 1 1 6 17 12 36 41 53 26 33 0 264 (1) 4.19 1.34 .50 .34 .00 .00 .27 .17 1.01 2.85 2.01 6.03 6.87 8.88 4.36 5.53 .00 44.22 (2) .29 .09 .03 .02 .00 .00 .01 .01 .07 .20 .14 .41 .47 .61 .30 .38 .00 3.03 13-18 9 1 0 0 0 0 0 1 0 0 9 17 14 22 17 10 0 100 (1) 1.51 .17 .00 .00 .00 .00 .00 .17 .00 .00 1.51 2.85 2.35 3.69 2.85 1.68 .00 16.75 (2) .10 .01 .00 .00 .00 .00 .00 .01 .00 .00 .10 .20 .16 .25 .20 .11 .00 1.15 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0' O 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .40 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 5 00 .C0 A1.L SPEEDS 53 18 17 9 7 5 14 15 16 27 42 79 82 93 63 57 0 597 (1) 8.88 3.02 2.85 1.51 1.17 .84 2.35 2.51 2.68 4.52 7.04 13.23 13.74 15.58 1( 55 9.55 .00 100.00 (2) .61 .21 .20 .10 .08 .06 .16 .17 .28 .31 .48 .91 .94 1.07 '.72 .66 .00 6.86 (1)= PERCENT OF ALL GOCD OBSERVATIONS FOR TMIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERICD Ca CALM (WIND SPEED LESS THAN OR FQUAL TO .95 MPH)

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SEABROOK JAN97-CE797 MET DATA JOINT FREQUENCY DISTRIBUTION (210-FOOT TOWER) 209.0 FT WIND DATA STABILITY CLASS ALL CLASS FRE2CEtCY (PER0ENTI = 100.00 WIND DIRECTION FROM SPEED N t :E NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRSL TOTAL MPH CALM 1 ft 0 0 0 3 1 0 . : 1 0 0 0 1 0 0 7 (1) .01 .00 .00 .00 .00 .03 .01 .00 .00 .00 .01 .00 .00 .00 .01 .00 .00 .09 (2) .01 .00 .00 .00 .00 .03 .01 .00 .00 .00 .01 .00 .00 .00 .01 .00 .00 .08 C-3 22 20 25 26 19 26 25 26 14 21 18 16 17 13 22 17 0 327 (1) .25 . 2. 3 .29 .30 .22 .30 .29 .30 .16 .24 .21 .38 .20 .15 .25 .20 .00 3.76 (2) .25 23 .29 .30 .22 .30 .29 .30 .16 .24 .21 .18 .20 .15 .25 .20 .00 3.76 4-7 113 63 79 60 82 81 100 77 f? 75 112 88 108 127 121 102 0 1457 (1) 1.30 .72 .91 .69 .94 .93 1.15 .89 79 .86 1.29 1.01 1.24 1.46 1.39 1.17 .00 16.75 (2) 1.30 ~2 .91 .69 .94 .93 1.15 .89 .79 .86 1.29 1.01 1.24 1.46 1.39 1.17 .00 16.75 8-12 190 113 100 113 94 115 186 160 152 174 245 321 335 484 334 208 0 3324 (1) 2.18 1.30 1.15 1.30 1.08 1,32 2.14 1.84 1.75 2.00 2.82 3.69 3.85 5.56 3.84 2.39 .00 38.21 (2) 2.18 1.30 1.15 1.30 1.08 1.32 2.14 1.84 1.75 2. 00 2.82 3.69 3.85 5.56 3.84 2.39 .00 38.21 13-18 80 69 87 41 41 28 84 95 60 87 272 381 361 517 378 84 0 2665 (1) .92 79 1.00 .47 .47 .32 .97 1.09 .69 1.00 3.13 4.38 4.15 5.94 4.34 .97 .00 30.63 (2) .92 .79 1.00 .47 .47 .32 .97 1.09 .69 1.00 3.13 4.38 4.15 5.94 4.34 .97 .00 30.63 19-24 16 18 33 4 15 13 9 10 13 7 57 47 82 219 120 8 0 671 (1) .18 .21 .38 .05 .17 .15 .10 .11 .15 .08 .66 .54 .94 2.52 1.'38 .09 .00 7.71 (2) .18 .21 .38 .05 .17 .15 .10 .11 .15 .08 .66 .54 .94 2.52 1.38 .09 .00 7.71 GT 24 7 8 36 3 22 8 1 1 0 2 14 4 26 83 29 5 0 249 (1) .08 .09 .41 .03 .25 .09 .01 .01 .00 .02 .16 .05 .30 .95 .33 .06 gC0 2.86 (2) .08 .09 .41 .03 .25 .09 .01 .01 00 .02 .16 .05 .30 .95 .33 .06 .00 2.86 ALL SPEEDS 429 291 360 247 273 274 406 369 308 366 719 857 929 1443 1005 424 0 8700 (1) 4.93 3.34 4.14 2.84 3.14 3.15 4.67 4.24 3.54 4.21 8.26 9.85 10.68 16.59 1F.55 4.87 .00 100.00 (2) 4.93 3.34 4.14 2.84 3.14 3.15 4.67 4.24 3.54 4.21 8.26 9.85 10.68 16.59 11.55 4.87 .00 100.0C (1)=PEROEtTT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD Ca CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPHn i

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1 ENCLOSURE 3 TO NYN-98062 i l l

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MEMORANI)UM DE&S-BOLTON To James M. Peschel- North Atlantic (SB 01-48) Date April 15.1998 Group # REG 98-049: SBP 98-024 From R. Brad Harvey- DE&S Bolton W.O.# 00459.00.0014.00.000 Subject DOSE

SUMMARY

FOR SEABROOK STATION I.M.S.# N02.03.04 File # 98-049.WPD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 1997

REFERENCE:

1. SBC-845," Estimated Doses from Liquid and Gaseous Effluent Discharges During 1997,"

Revision 0.

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BACKGROUND: I Technical Specification 6.8.1.4 requires that an Annual Radioactive Effluent Release Report be l submitted by May 1 of each year. The report shall include an assessment of radiation doses to members of the public due to radioactive liquid and gaseous effluents released during the previous year.

1 DISCUSSION:

Attached is a report which provides the doses resulting from 1997 liquid and gaseous effluents as well as direct shine from Seabrook Station and a description of the methods used to calculate them. Table A of the report summarizes the quarterly offsite doses to members of the public.

The report indicates the reference sources for pathways models, environmental parameters, and input assumptions used in the dose calculation. The calculated doses, as shown on Table A. were well below all Technical Specification limits. Documentation for the dose calculation can be found in SBC-845 (Reference 1).

Also attached at the end of the 1997 dose report are revisions (errata) to the first page of Table A for the 1992 and 1995 Effluent Dose Reports. These pages correct the argan doses previously reported for the onsite (special receptor) Science and Nature Center (Ed Center) and the " Rocks" These revisions are the result of a conservative error found in the ce nputer code ATMODOS which miscalculated organ doses from iodine, tritium, and particulite releases whenever an

! occupancy correction factor other than 1.0 was used. The corrected dt ses do not change either the value reported for the maximum offsite receptor (controlling point) or the original

, determination that the plant was in compliance with all dose limits for the year.

i Please do not hesitate to contact me (Bolton x2727) if there are any questions.

I James M. Peschel - North Atlantic (SB 01-48)

[ April 15,1998 j Page 2 i-3ML/ % /

R. Brad Harvey, Lead Engiheer Peter S. Littlefigid, Manager

{ Radiological Engineering Group Radiological Engineering Group Environmental Health & Safety Environmental Health & Safety Attachment c: W.A. DiProfio (SB 49-SS)

J. Kwasnik (SB 02-12) .

P.S. Littlefield

R.A. Marcello W.J. Merritt M.S. Strum L.R. Tardiff(SB 49-CH)

J.M. Vargas (SB 01-62) l' l.

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1 Seabrook Station Radiological Effluent Impact Assessment For 1997 (Annual Radioactive Effluent Release Report) l I. Summary 1

)

I Doses resulting from liquid and gaseous effluents from Seabrook Station during 1997 were calculated in accordance with Method II as defined in the Station Offsite Dose Calculation Manual j (ODCM). The calculational methods used follow the models in Regulatory Guide 1.109. The calculations included maximum whole body doses and organ doses from all liqui.d releases, l

maximum offsite organ doses resulting from airbome iodines, tritium and particulate radionuclides, I and maximum offsite beta air and gamma air doses from airborne noble gases. Doses were also calculated for the special receptor locations inside the site boundary: the Science and Nature Center !

and the " Rocks". In addition, the potential direct dose froth plant operation was evaluated. Doses from effluent releases and direct shine during 1997 are summarized in Table A.

The calculated maximum annual total body dose and the maximum organ dose from liquid effluents represent 0.02% and 0.01% of the annual dose limits established by Technical Specification 3.11.1.2 (3 mrem total body and 10 mrem organ). The calculated annual maximum dose from airbome iodine, tritium and particulate radionuclides for offsite receptor locations represents 0.16% of the dose limit established by Technical Specification 3.11.2.3 (15 mrem organ),

whereas the calculated maximum annual beta air and gamma air doses from airborne noble gases for offsite receptor locations represent 0.12% and 0.08% of the dose limits established by Technical Specification 3.11.2.2 (20 mrad beta air and 10 mrad gamma air). For onsite special receptors, the i calculated annual doses from airborne effluents for both the Science and Nature Center and the

" Rocks" were also well below all Technical Specification dose limits.

The sum of the maximum whole body doses from all exposure pathways for the liquid and gaseous effluents, plus the direct whole body dose from station operation, was 1.97E-02 mrem to

- a hypothetical individual at or beyond the site boundary. This whole body dose represents 0.08%

of the annual whole body dose limit (25 mrem) for a member of the public as set forth in 40CFR 190, L\RBlnSB\EIFLNT.97 -l-

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i and demonstrates compliance with that code. The maximum organ dose from all exposure pathways including direct dose was 3.11E-02 mrem. This represents 0.12% of the annual organ dose limit of 25 mrem to other organs, as set forth in EPA's environmental radiation standard for the uranium fuel cycle,40CFR190. l l

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i JARBinSB\ERINT.97 l 11. Method for Calculating the Total Body and Maximum Organ Doses Resultina from Liquid l

Releases l

The computer code IDLE, which is consistent with the models in Regulatory Guide 1.109 (Reference 1), was used to calculate the total body and organ doses resulting from liquid effluents !

from Seabrook Station. The general equations A-3, A-4, A-5, A-6 and A-7 from Regulatory Guide 1.109 are applied in IDLE. The total body doses and the organ doses are evaluated for each of the four age groups (i.e., infant, child, teen and adult) to determine the maximum total body dose and maximum organ dose via all existing exposure pathways (i.e., fish and aquatic invertebrate ingestion, and shoreline exposure) to an age-dependent individual. The values for the various factors considered in equations A-3 through A-7 have been taken from Regulatcry Guide 1.109 and the Station Offsite Dose Calculation Manual (ODCM) (Reference 2). The specific values used for the usage factor (U,,), mixing ratio (M,), bioaccumulation factor (B,,), dose factors (D,3,i), transit time

~

(t,), transfer constant from water to sediment (K,), exposure time for sediment or soil (t ), and shore width factor (W) are provided by the reference sources as summarized in Table B. The flow rate of the liquid effluent (F) and the radionuclide activities (Q,) are measured specifically prior to each 4

liquid release. The values for halflives for radionuclides (T)i and their radioactive decay constants (A,) have been taken from Kocher (Reference 3).

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The exposure pathways considered in the calculations of total body and maxirnum organ ji doses resulting from liquid discharges from Seabrook Station have been limited to ingestion of aquatic foods and exposure to shoreline deposits. The dose calculations do not include the ingestion of potable water and inigated vegetation as potential exposure pathways because the liquid effluents from the plant are discharged into salt water.

Table A presents the calculated liquid pathway doses for each calendar quaner and also the total for the year.

JARBH\SB\EHLNT,97 r .

III. Method for Calculating the Gamma and Beta Air Doses from Noble Gases The computer codes AIRAD and AEOLUS 2 were used for the calculation of both the gamma and beta air doses resulting from noble gases present in gaseous effluents released from Seabrook Station. The features and use of AEOLUS 2 for the calet.lation of atmospheric dispersion factors (i.e., Chi /Q factors) from recorded meteorological data (i.e., meteorological data-measurements taken during the time of the release) are described in section B.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of gas releases are calculated by i AEOLUS 2 and used in the gamma and beta air dose calculations performed by AIRAD. AIRAD is consistent with the models presented in kegulatory Guide 1.109, general equations B4 and B-5.

l The values for the dose factors, DF,Y and DFf, have been taken from Table B-1 in Regulatoiy Guide 1.109.

i Table A lists the calculated air doses for each calendar quarter, and the total for the year.

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JARBH\SB\EFFLNT.97 -4 l

IV. Method for Calculating the Critical Organ Dose Resulting from Iodines, Tritium and Paniculates with T mGreater than 8 Days in Gaseous Releases The computer codes AEOLUS 2 and ATMODOS were used for the calculation of the organ doses resulting from iodines, tritium and paniculates with half-lives greater than 8 days present in gaseous effluents released from Seabrook Station. The features and use of AEOLUS 2 for the calculation of atmospheric dispersion factors (i.e., Chi /Q factors) from recorded meteorological data (i.e., meteorological data measurements taken during the time of the release) are described in section B.7.3.2 of Seabrook's ODCM. Meteorological dispersion factors concurrent with periods of gas releases were calculated by AEOLUS 2 and used in the dose calculations by AtMODOS.

ATMODOS calculates the organ doses ( i.e., dose to bone, liver, kidney, lung, lower large intestine, total body, and skin) due to the presence of radionuclides other than noble gases in gaseous effluents, and is consistent with the models presented in Appendix C of Regulatory Guide 1.109. The

~

pathways considered in the dose calculations are the ground plane, inhalation, and ingestion of stored vegetables, fresh garden vegetables, and milk. The critical organ dose is determined for the offsite location (e.g., site boundary, nearest resident or farm) of receptor pathways as identified in the most recent annual land use census. The total body dose contributions via the ground plane and inhalation pathways as calculated by ATMODOS have also been included in the total body dose estimates for the special receptor locations inside the site boundty. Regulatory Guide 1.109 equations C-1 through C-13 are applied in the ATMODOS calculation of the critical organ doses. The input data and assumptions are those provided in Appendix C of the Regulatory Guide, except where site-specific data and assumptions have been identified in Tables B.7-2 and B.7-3 of Seabrook's ODCM.

These two ODCM tables provide the options for special conditions, depending on the type of receptor being evaluated at a specific location, that can be applied in Method II calculations. The receptor type controls the exposure pathways for calculational purposes. The receptor types used in the dose calculations were a resident receptor (which considered the ground plane, inhalation and vegetable ingestion exposure pathways), a milk receptor (which considered the ground plane, inhalation, vegetable and milk ingestion exposure pathways) and a boundary and radius receptor (both of which considered the ground plane and inhalation exposure pathways). The resident and milk receptor locations for the various sector were based on the 1997 land use census data for JARDmsBiErTINT.97 Seabrook Station (Table D). The radius receptor locations were applied at several distances in the prevalent downwind secWt to insure that the location of the maximum doses were not overlooked.

Depletion of the plume during transport is considered by AEOLUS 2 in the calculations of atmospheric dispersion factors (e.g., calculation of[X/Q] ). A shielding factor (S p) of 0.7 is applied for residential structures. The source for the values of the various factors used in Regulatory Guide 1.109 dose equations C-1 through C-13 are summarized in Table C, s

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V. References 1.

Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR Part 50, Appendix I, Reg. Guide 1.109, Rev 1, Oct.1977.

2. Station Offsite Dose Calculation Manual, Rev 18.

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3. Kocher, D.C., Dose-Rate Conversion Factors for Exposure to Photons aiid Electrons, Health 1 Physics, Vol. 45, No. 3, Sept.1983.

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TABLE A i (Sheet 1)

Seabrook Station 1997 Annual Radioactive Effluent Release Report l

l MaximumW Off-Site Doses and Dose Commitments to Members of the Public i

Dose (mrem)*

lst 2r.d 3rd 4th

, Quarter Quarter Quarter Quarter Yeark)

Liquid Effluents:

Total Body Dose 1.80E-04 2.31E-04 2.06E-04 6.19E-05 6.79E-04 '

(1) (1). (1) (1)

Organ Dose 4

i 3.16E-04 6.47E-04 3.48E-04 1.66EM 1.48E-03 i

/ (2) (3) (3) (2)

Airborne Effluents:

Organ Dose from lodines, 1.22E-03 1.53B-02 4.91E-03 3.31E-03 2.47E-02 Tritium, and Puticulates (4) (5) (6) (7)

Noble Gases Beta Air 1.39E-03 2.29E-02 1.18E-04 3.90E-05 2.44E-02 (mrad) (8) (9) (10) (11)

Gamma ;7.04E-04 7.35E-03 1.13E-04 1.27E-05 8.18E-03 Air (8) (9) (9) (11) 1 (mrad)

Doses (mrem) at Receptor Locations Inside Site Boundary *:

Science and Nature Center (SW,488m): !

Beta Air Dose (mrad) 3.15E-06 9.148-05 4.26E-07 1.75E-08 9.50E-05 Gamma Air Dose (mrad) 1.27E-06 2.41E-05 3.37E-07 4.80E-09 2.57E-05 Organ Dose (mrem) 5.77E-07 5.59E-06 2.66E-06 1.79E-06 1.06E-05 (12) (12) (12) (13)

The " Rocks" (NE/ENE,244m):

Beta Air Dose (mrad) 3.56E-04 2.07E-03 2.22E-05 2.94E-06 2.45E-03 l l Gamma Air Dose (mrad) 8.89E-05 3.62E-04 6.41E-06 4.31E-07 4.58E@

Organ Dose (mrem) 6.48E-05 2.13E-04 1.76E-04 2.00E-04 6.54E-04 (12) (12) (12) (13)

Direct Dose From Plant Operation") 0 1

J.\RBif\SB\LFFLNT.97 TABLE A (Sheet 2)

Seabrook Station 1997 Annual Radioactive Effluent Release Report NOTES:

l '(a) " Maximum means the largest fraction of conesponding 10CFR50, Appendix I, dose design objective.

l-l- (b)' The numbered footnotes indicate the age group, organ, and location (compass sector and distance from stack in meters) of the dose receptor, where appropriate.

(1) Adult.

j (2) Bone of a child.

(3) GI-LLI of an adult.

(4) Thyroid of a child, ESE 2400m..

(5) Thyroid of a child, NW 1000m. .

(6) Thyroid of a child, W 1000m.

(7) Liver, kidney, lung, GI-LLI, thyroid, and whole body of a child, SSE 1000m.

(8) ESE 2276m.

(9) SW 1022m.

(10) W 974m.

(11) NW 914m.

(12) Thyroid of a teen.

(13) Liver, kidney, lung, GI-LLI, thyroid, and whole body of a teen.

(c) " Maximum" dose for the year is the sum of the maximum doses for each quarter. This results in a conservative yearly dose estimate, but still well within the limits of 10CFR50.

_(d) For each special receptor location, the whole body and organ doses calculated for the airbome effluent releases were adjusted by the occupancy factor provided in Seabrook's ODCM (i.e.,0.0014 for the Science and Nature Center and 0.0076 for the " Rocks").

(c) Only station sources are considered since there are no other facilities within five miles of Seabrook Station. 1997 data for the closest off-site environmental TLD locations in each sector (as listed in Table B.4-1 of Seabrook's ODCM) were compared to preoperation data from 1986-1988 for the same locations. No statistical difference which could be attributed to station sources was identified.

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TABLE B '

l (Sheet 1)

Seabrook Station 1997 Annual Radioactive Effluent Release Report ;

Sources of the Values of Factors Used in Liguid Dose Equations I

Factor Definition Source U,, Usage factor Table B.7-1, Station ODCM M, Mixing ratio Section B.7.1, Station ODCM (value=0.1 l

for aquatic foods and 0.025 for shoreline)

B,, Equilibrium bioaccumulation Table A-1, Reg. Guide 1.109 factor D,;,, Dose factor Tables E-11 through E-14, R.G.1.109 t, Nuclide transit time Section B.7.1, Station ODCM K, Transfer coefficient from water to Reg. Guide 1.109 sediment ts Soil exposure time Table B.7-2, Station ODCM W Shoreline width factor Table A-2, Reg. Guide 1.109 (value=0.5)

I l JARBinSB\ErTMT.97 1

O TABLE C (Sheet 1)

Seabrook Station 1997 Annual Radioactive Effluent Release Report Sources of Values for the Factors Used in Dose Equations for Gaseous Releases Factor Definition Source

t. Period of activity buildup in Reg. Guide 1.109 sediment or soil A; Nuclide decay constant Kocher (Reference 3) 1 DFGa Ground plane dose factor Table E-6, Reg. Guide 1.109 '

IX/Ol Atmospheric dispersion factor Calculated by AEOLUS 2 (Mod 5) 1 R, Breathing rate Table B.7-3, Station ODCM DFAa, hihalation dose factor Tables E-7 through E-10, R.G.I.109

d. Nuclide deposition rate Reg. Guide 1.109 P Soil surface density Table B.7-2, Station ODCM '

t, Crop, leafy vegetable, or pasture Table B.7-2, Station ODCM grass exposure period tn Average time from crop harvest to Table B.7-2, Station ODCM consumption Y, Agricultural productivity by unit Table B.7-2, Station ODCM area r Fraction of deposited activity Table E-15, Reg. Guide 1.109 retained on crops, leafy vegetables, or pasture grass B, 3 Stable element transfer coefficient Table E-1, Reg. Guide 1.109 from soil to produce, leafy vegetable, or pasture grass p Fractional equilibrium ratio Reg. Guide 1.109 H Ambient absolute humidity Table B.7-2, Station ODCM F, Stable element transfer coefficient Tables E-1 and E-2, R.G.1.109 from feed to milk tr Average time from feed to milk to Reg. Guide 1.109 consumption f, Fraction of the year that animals Table B.7-2, Station ODCM graze on pasture naamss m wrm l

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I TABLE C (Sheet 2) l Seabrook Station 1997 Annual Radioactive Effluent Release Report Factor Definition Source f, Fraction of animal daily feed that Table B.7-2, Station ODCM is pasture grass F, Stable element transfer coefficient Table E-1, Reg. Guide 1.109 I

from feed to meat t, Average time from meat animal Table E-15, Reg. Guide 1.109 slaughter to consumption '

DFL. Ingestion dose factor Tables E-11 through E-14, R.G.I.109

! U,v Annualintake of produce Table B.7-3, Station ODCM U,'a , Annualintake of milk Table B.7-3, Station ODCM U,F Annual intake of meat Table B.7-3, Station ODCM l U,' Annualintake ofleafy vegetables Table B.7-3, Station ODCM f, Ingestion rate fractions for garden Reg. Guide 1.109 produce f, Ingestion rate fractions for garden Reg. Guide 1.109 leafy vegetables A. Rate constant for activity removal Table E-15, Reg. Guide 1.109 from plant and leaf surfaces by weathering Qg Animal consumption rate Table E-3, Reg. Guide 1.109 naamsmrnmT.97 J

S TABLE D (Sheet 1)

S_gbrook Station .

1997 Annual Radioactive Effluent Release Report Recentor Locations

for Seabrook Station Milk Animals Nearest Nearest within 5 Mile -

Resident Garden Radius Sector mile (km) mile (km) mile (km) _

N 0.6 (l.0) 2.6 (4.2) ---

l NNE 2.0 (3.2) 2.0 (3.2) - l NE 1.5 (2.4) 2.0 (3.2) --

ENE 1.5 (2.4) ---

E 1.6 (2.6) -- ---

ESE 1.5 (2.4) - ---

SE 1.5 (2.4) - --- ---

SSE 0.6 (l.0) 0.6 (l .0) - '

S '

0.6 (1.0) 0.7 (1.1) ---

l SSW 0.5 (0.8) 0.5 (0.8) -

SW 0.6 (l.0) -

3.2 (5.2) l WSW 0.6 (1.0) 0.6 (1.0) --

l W 0.6 (1.0) 0.6 (1.0) ---

WNW 0.6 (l.0) 0.7 (1.1) 3.0 (4.8) j 3.8 (6.1) p 4.8 (7.7)

NW 0.6 (l.0) 0.7 (l.1) 4.4 (7.1)

NNW 0.7 (1.1) 0.7 (1.1) 3.4 (5.5) l

Locations based on 1997 Land Use Census.

L\RBif\SB'CFFW.9i -

ERRATA TABLE A Rev. 1 Seabrook Station Effluent and Waste Disposal Semiannual Report {

1992 l

i Maximum Of f-Site Doses and Dose Commitments to Members of the Public Dose (mrem)"

ist 2nd 3rd 4th Quarter Quarter Quarter Quarter Year

Liquid Effluents:

Total Body Dose 4.8e-04 4.4e-04 3.8e-04 3.8e-04 1.7e-03 Organ Dose {

2.8e-03 2.2e-03 1.8e-03 1.7e-03 .8.5e-03 I (1) (1) (1) (1)

Airborne Effluents:

Iodines, Tritium, and 9.5e-06 3.0e-05 4.le-04 6.8e-04 1.le-03 Particulates (2) (3) (4) (5)

I Noble Gases Beta Air 1.le-04 2.Se-05 8.5e-06 9.le-07 1.4e-04 l (mrad) (6) (7) (8) (9) i Gamma 1.5e-04 4.le-05 3.5e-06 1.8e-06 2.0e-04 ;

Air (6) (7) (8) (9)

(mrad?

Doses (mrem) at Receptor Locations Inside Site Boundary (d):

Education Center (SW, 485m)

Beta Air Dose (mrad) --- 5.3e-05 2.5e-07 ---

5.3e-05 Gamma Air Dose (mrad) ---

7.9e-05 3.5e-06 ---

8.3e-05 Organ Dose (mrem) ---

1.0e-08 5.0e-07 2.7e-07 7.8e-07 l (10) (11) (la)

The " Rocks" (NE/ENE, 244m)

Beta Air Dose (mrad) 6.5e-04 4,8e-05 2.0e-05 ---

7.2e-04 Gamms Air Dose (mrad) 5.7e-04 2.7e-05 5.le-06 ---

6.0e-04 Organ Dose (mrem) 4.5e-07 3.7e-08 1.9e-05 1.4e-05 3.4e-05 l (10) (10) (11) (11)

I J r \RBH\SB\EFFIJC. 92 9 April 15, 1998 l

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i ERRATA TABLE A Rev. 1 12AhfDQi Station

- Effluent and Waste Disoosal Annual Reoort 1995 l Maximum"' Off Site Doses and Dose Commitments to Members of the Public Dose (mrem)"'

1st 2nd 3rd 4th Quarter Quarter Guarter Quarter Yeark '

Liquid Effluents:

Total. Body Dose 9.4E-05 8.1E-05 1.0E 04 4.0E-04 .6.8E-04 (1) (2) (1) (2)

Organ Dose -4.2E-04 3.2E-04 4.1E-04 1.2E-03 2.4E-03 (3) (3) (3) (3)

Airborne Effluents:

Organ Dose from lodines, 2.4E-04 1.1E-04 1.8E-05 2.0E 03 2.4E-03 Tritium, and Particulates (4) (5) (6) (7) ]

Noble Gases Beta Air 1.9E-05 2.2E-05 9.6E-05 9.2E-05 2.3E-04 (mrad) (8) (9) (10) (11)

Gamma 3.3E-05 4.3E-05 2.3E-04 1.7E-04 4.8E-04 Air (8) (12) (10) (11)

(mrad) j Doses (mrem) at Receptor Locations inside Site Boundary"':

,, Science and Nature Center (SW, 488m):

Beta Air Dose (mrad) 7.0E-08 ---

7.8E-09 ---

7.8E-08 Gamma Air Dose (mrad) 9.6E-08 ---

4.8E-08 ---

1.4E-07

Organ Dose (mrem) 6.3E-09 ---

1.4E-09 7.4E-07 7.4E-07 1 3 (13) (14) (15) i f \

The " Rocks" (NE/ENE, 244m):

Beta Air Dose (mrad) 1.9E-06 7.7E-06 2.9E 06 1.5E-05 2.8E-05 Gamma Air Oose (mrad) 1.6E-06 4.0E-06 2.5E-06 9.3E-06 1.7E-05 Organ Dose (mrem) 4.4E-07 7.0E-06 3.0E-07 7.2E-05 7.9E-05 l (13) (13) -(13) (15)

Direct Dose-From Plant 0 l Operation"' '

J:\RBH\sBMFFLNT.95 April 15. 1998 l

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1 re co m or, cory [ M O PROGRAM MANUAL '"~' North j

' Atlantic.

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Offsite Dose Calculation Manual i

1 O

lMFOR h4 TIO N ONty Effective Date: ___ 02/25/98 ODCM Manual Owner:

Rev.18 D. A. Robinson O

qwnaam

DISCIAIMER OF RESPONSIBILITY This document was prepared by Yankee Atomic Electric Company (" Yankee"). The use of information contained in this document by anyone other than Yankee, or the Organization for which the document was prepared under contract, is not authorized and, with resoect to any unauthorized use, neither Yankee nor its officers, directors, agents, or employees assume any obligation, responsibility, or liability or make any warranty or representation as to the accuracy or completeness of the t material contained in this document.

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Page 1 of 1 ODCM Rev. 16

ABSTRACT l The Offsite Dose Calculation Manual (ODCM) is divided into two parts: (1) the in-plant Radiological Effluent Monitoring Program requirements for liquid and gas sampling and analysis, along with the Radiological Environmental Monitoring Program requirements (Part A); and (2) approved methods to determine effluent monitor setpoint values and estimates of doses and radionuclide concentrations occurring beyond the boundaries of Seabrook Station resulting from normal Station operation (Part B).

The sampling and analysis programs in Part A provide the inputs for the models of Part B in order to calculate offsite doses and radionuclide concentrations necessary to determine compliance with the dose and concentration requirements of the Station Technical Specification 3/4.11. The Radiological Environmental Monitoring Program required by Technical Specification 3/4.12 and outlined within this manual provides the means to determine that measurable concentrations of radioactive materials released as a result of the operation of Seabrook Station are not significantly higher than expected.

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Page 1 of 1 ODCM Rev. 16

OFFSITE DOSE CALCUIATION MANUAL (ODCM) r\

) TABLE OF CONTENTS CONTENT E691 PART A: RADIOIDGICAL EFFIRENT CONTROL AND ENVIROtGENTAL MONITORING PROGRAMS

1.0 INTRODUCTION

A.1-1

7. 0 RESPONSIBILITIES (PART A) A.2-1 3.0 DEFINITIONS A.3-1 3.1 GASEOUS RADWASTE TREATMENT SYSTEM A.3-1 3.2 ffEMBER(S) OF THE PUBLIC A.3-1 3.3 UNRESTRICTED AREA A.3-1 3.4 VENTIIATION EXHAUST TREATMENT SYSTEM A.3-1 i

4.0 CONTROL AND SURVEILLANCE REQUIREMENTS: APPLICABILITY A.4-1 l Q '

V 5.0 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION A.5-1 5.1 LIQUIDS A.5-1 5.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION A.5-6 6.0 RADIOACTIVE LIQUID EFFLUENTS A.6-1 6.1 CONCENTRATION A.6-1 1

6.2 DOSE A.6-8 6.3 LIQUID RADWASTE TREATMENT SYSTDi A.6-10 7.0 RADIOACTIVE LIQUID EFFLUENTS A.7.1 7.1 DOSE RATE A.7.1 7.2 DOSE - NOBLE GASES A.7-7 Page 1 ODCM Rev. 18

TABLE OF CONTENTS l

CONTENT E6GE 9

PART A: RADIOLDGICAL EFFIDENT CONTROL AND ENVIRONMENIAL MONITORING PROGRAMS 7.3 DOSE - IODINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICUIATE FORM A.7-9 7.4 GASEOUS RADVASTE TREATMENT SYSTEM A.7-11 8.0 TOTAL DOSE A.8-1 9.0 EADIOIDGICAL ENVIRONMENTAL MONITORING A.9-1 9.1 MONITORING PROGRAM A.9-1 9.2 IAND USE CENSUS A.9-ll 9.3 INTERLABORATORY COMPARISON PROGRAM A.9-13 10.0 REPORTS A.10-1 10.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A.10-1 10.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A.10-2 PART B: RADIOIDGICAL CALCUIATIONAL METHODS AND PARAMETERS l

1.0 INTRODUCTION

B.1-1 1.1 RESPONSIBILITIES FOR PART B B.1-1 1.2

SUMMARY

OF METHODS, DOSE FACTORS, LIMITS, CONSTANTS, VARIABLES AND DEFINITIONS B.1-2 2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS B.2-1 2.1 METHOD TO DETERMINE FtN' AND C2 "' B.2-1 2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE B.2-2 2.2.1 Waste Test Tanks B.2-2 2.2.2 Turbine Building Sump B.2-3 Page 2 ODCM Rev. 18

TABLE OF CONTENTS CONTENT fA9_E

(

PART B: RADIOIDGICAL CAIEUIATIONAL METHODS AND PARAMETERS 2.0 METHOD TO CALCUIATE OFF-SITE LIQUID CONCENTRATIONS 2.2.3 Steam Generator Blowdown Flash Tank B.2-3 2.2.4 Primary Component Cooling Water (PCCW) System B.2-3 3.0 0FF-SITE DOSE CALCUIATION METHODS B.3-1 3.1 INTRODUCTORY CONCEPTS B.3-2 3.2 METHOD TO CALCUIATE THE TOTAL BODY DOSE FROM LIQUID RELEASES B.3-4 3.2.1 Method I B.3-4 3.2.2 Method II B.3-5 3.3 METHOD TO CALCULATE MAXIMUM ORGAN DOSE FROM LIQUID RELEASES B.3-6 (3 3.3.1 Method I B.3-6 V 3.3.2 Method II B.3-7 3.4 METHOD TO CALCULATE THE TOTAL BODY DOSE RATE FROM NOBLE CASES B.3 8 j l

3.4.1 Method I B.3 8 3.4.2 Method II B.3-10 3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES B.3-11 1

3.5.1 Method I B.3 11 I 3.5.2 Method II B.3 14 3.6 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM AND PARTICUIATES WITH Tu2 GREATER l THAN 8 DAYS B.3-15

-3.6.1 Method I B.3-15 3.6.2 Method II B.3-18 O

Page 3 ODCM Rev. 18

TABLE OF CONTENTS CONTENT ZAGE O

PART B: RADIOIDGICAL CAIEUIATIONAL METHODS AND Pt.RAMETERS 3.7 METHOD TO CALCUIATE THE GAMMA AIR DOSE FROM NOBLE GASES B.3-19 3.7.1 Method I B.3-19 3.7.2 Method II B.3-21 3.8 METEOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE GASES B.3-22 3.8.1 Method I B.3-22 3.8.2 Method II B.3-24 3.9 METHOD TO CALCULATE THE CRITICAL ORGAN DOSE FROM 10 DINES, TRITIUM AND PARTICU1ATES B.3-25 3.9.1 Method I B.3-25 3.9.2 Method II B.3-27 3.10 METHOD TO CALCUIATE DIRECT DOSE FROM PIANT OPERATION B.3-28 3.10.1 Method B.3-28 3.11 DOSE PROJECTIONS B.3-29 l

B.3-29

! 3.11.1 Liquid Dose Projections l 3.11.2 Gaseous Dose Projections .3-29 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B.4-1 5.0 SETPOINT DETERMINATIONS B.5-1 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS B.5-1 5.1.1 Liquid Waste Test Tank Monitor (RM 6509) B.5-1 5.1.2 Turbine Building Drair.s Liquid Effluent Monitor (RM-6521) B.5-5 5.1.3 Steam Generator Blowdown Liquid Sample Monitor (RM-6519) B.5-6 5.1.4 PCCW Head Tank Rate-of-Change Alarm Setpoint B.5-6 Page 4 ODCM Rev. 18

TABLE OF CONTENTS CONTENT 1691 PART B: RADIOIDGICAL CAIEUIATI0tuL METHODS AND PARAMETERS 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 1

1 5.1.5 PCCW Radiation Monitor B.5-7 )

1 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS B.5-8 l

5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1, 2 and 3) B.5-8 5.2.2 Wasta Gas System Monitors (RM-6504 and RM-6503) B.5-11 5.2.3 Main Condenser Air Evacuation Monitor (RM-6505) B.5-12 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS B.6 1 7.0 BASES FOR DOSE CALCUIATION METHODS B.7-1 7.1 LIQUID RELEASE DOSE CALCULATIONS B.7-1 l p

7.1.1 Dose to the Total Body E.7-4 7.1.2 Dose to the Critical Organ B.7-4 1

7.2 GASEOUS RELEASE DOSE CALCULATIONS B.7-7 ]

1 7.2.1 Total Body Dose Rate From Noble Gases B.7-7 7.2.2 Skin Dose Rate From Noble Gases B.7-9 7.2.3 Critical Organ Dose Rate From Iodines, Tritium and Particulates With Half Lives Greater Than j Eight Days B.7-12 )

7.2.4 Camma Dose to Air From Noble Gases B.7-14 7.2.5 Beta Dose to Air From Noble Gases B.7-16 !

7.2.6 Dose to Critical Organ From Iodines, Tritium and j Particulates With Half-Lives Greater Than Eight ;

Days B.7-18 7.2.7 Special Receptor Gaseous Release Dose Calculations B.7-20 7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS ,

FG IMPORTANT EXPOSURE PATHWAYS B.7-34 O 7.3.1 Receptor Locations B.7-34 Page 5 ODCM Rev. 18

TABLE OF CONTENTS CONTENT f.693 O

PART B: RADIOIDGICAL CALCULATIONAL METHODS AND PARAMETERS 7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS 7.3.2 Seabrook Station Atmospheric Dispersion Model B.7-35 l

7.3.3 Average Atmospheric Dispersion Factors for Receptors B.7-35 8.0 BASES FOR LIQUID AND GASEOUS MONITOR SETPOINTS B.8-1 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT B.8-1 8.2 BASIS FOR THE PIANT VENT WIDE RANGE CAS MONITOR SETPOINTS B.8-5 8.3 BASIS FOR PCCW HEAD TANK RATE-OF-CHANGE AIARM SETPOINT B.8-10 8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) B.8-11 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) B.8-14 l 8.5.1 Example for the Air Evacuation Monitor Setpoint During Normal Operations B.8-14 8.5.2 Example for the Air Evacuation Monitor Setpoint During Start Up (Hogging Mode) B.8-16 REFERENCES R-1 APPENDIX A: METHOD I DOSE CONVERSION FACTORS A-1 l APPENDIX B: CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND B-1 TAKEN FROM 10 CFR 20.1-20.602, APPENDIX B APPENDIX C: EMS SOFTWARE DOCUMENTATION C-1 APPENDIX X: ODCM, REV. 18 (PENDING NRC APPROVAL) X-1 APPENDIX Y: 10 CFR 50.59 EVALUATION Y-1 O

Page 6 ODCM Rev. 18

1 TABLE OF CONTENTS NUMBER LIST OF vaRTRN AND FICERES E PART A TARTXR A.3.1 Frequency Notation A.3-2 A 3.2 Operational Modes A.3-2 A.5.1-1 Radioactive Liquid Effluent Monitoring Instrumentation A.5-2 A.5.1-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements A.5-4 A.S.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation A.5-7 A.S.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements A.5-9 A.6.1-1 Radioactive Liquid Waste Sampling and Analysis Program A.6-2 4

A.7.1-1 Radioactive Gaseous Waste Sampling and Analysis Program A.7-3 O A.9.1-1 Radiological Environmental Monitoring Program A.9-3 A.9.1-2 Detection Capabilities for Environmental Sample Analysis **f

A.9-7 A.9.1-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples A 9-10 PART & TABLES B.1-1 Susanary of Radiological Effluent Part A Controls and Implementing Equations B.1-3 B.1-2 Summary of Method I Equations to Calculate Unrestricted Area Liquid Concentrations B.1-6 B.1-3 Summary of Method I Equations to Calculate Off-Site Doses from Liquid Releases B.1-7 B.1-4 Summaary of Method I Equations to Calculate Dose Rates B.1-8 Page 7 ODCM Rev. 18

i TABLE OF CONTENTS ]

{

1 NUMBER LIST OF TABIE.S AND FIGURES ZA_GE PART B TABIE.S (Continued)

B.1-5 Sumary of Method I Equations to Calculate Doses to Air from Noble Cases B.1-11 B.1-6 Summary of Method I Equations to Calculate Dose to an Individual from Tritium, Iodine and Particulates B.1-13 B.1-7 Summary of Methods for Setpoint Determinations B.1-14 B.1-8 Summary of Variables B.1-15 B.1-9 Definition of Terms 3.1-22 B.1-10 Dose Factors Specific for Seabrook Station for Noble Gas Releases B.1-23 l B.1-11 Dose Factors Specific for Seabrook Station for Liquid Releases B.1-24 B.1-12 Dose and Dose Rate Factors Specific for Seabrook Station for Iodines, Tritium and Particulate Releases B.1-25 B.1-13 Combined Skin Dose Factors Specific for Seabrook Station Special Receptors for Noble Gas Release B.1-26 B.1-14 Dose and Dose Rate Factors Specific for the Science and Nature Center for Iodine, Tritium, and Particulate Releases B.1-27 B.1-15 Dose and Dose Rate Factors Specific for the " Rocks" for Iodine, Tritium, and Particulate Releases B.1-28 B.4-1 Radiological Environmental Monitoring Stations B.4-2 B.7-1 Usage Factors for Various Liquid Pathways at Seabrook B.7-6 Station B.7-2 Environmental Parameters for Gaseous Effluents at Seabrook Station B.7-31 O

Page 8 ODCM Rev. 18

]

TABLE OF CONTENTS NUMBER LIST OF TABIES AND FIGURES fKr1 PART B TABIES (Continued)

B.7-3 Usage Factors for Various Gaseous Pathways at Seabrook Station B.7-33 B 7-4 Seabrook Station Long-Tern Average Dispersion Factors Primary Vent Stack B.7-38 B.7-5 Seabrook Station Long-Tern Average Dispersion Factors for Special (On-Site) Receptors Primary vent Stack B.7-39 B.7-6 Seabrook Station Long-Term Atmospheric Diffusion and Deposition Factors Ground-Level Release Pathway B.7-40 PART B FIGURES B.4-1 Radiological Environmental Monitoring Locations Within 4 kilometers of Seabrook Station B.4-5 B.4-2 Radiological Environmental Monitoring locations Between 4 kilometers and 12 kilometers from Seabrook Station B.4-6 B.4-3 Radiological Environmental Monitoring Locations Outside 12 kilometers of Seabrook Station B.4-7 B.4-4 Direct Radiation Monitoring locations Within 4 kilometers of Seabrook Station B.4-8 B.4-5 Direct Radiation Monitoring Locations Between 4 kilometers and 12 kilometers from Seabrook Station B.4-9 B.4-6 Direct Radiation Monitoring Locations Outside 12 kilometers of Seabrook Station B.4-10 B.6-1 Liquid Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6-2 B.6-2 Caseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6-3 O

V Page 9 ODCM Rev. 18

IJST OF EFFECTIVE PAGES FAGE E fAGE REL. f. AGE BEL.

O Cover 18 B.1-16 17 B.4-4 16 B.1-17 16 B.4-5 17 Abstract 16 B.1-18 16 B.4-6 17 B.1-19 17 B.4-7 16 Toc 1 - 9 18 B.1-20 17 B.4-8 16 B.1-21 17 B.4-9 16 IDEP 1 & 2 18 B.1-22 17 B.4-10 16 B.1-23 16 A.1 1 16 B.1-24 16 B.5-1 17 B.1-25 16 B.5-2 17 A.2-1 16 B.1-26 16 B.5-3 17 B.1-27 16 B.5-4 17 A.3-1 16 B.1-28 16 B.5-5 17 A.3-2 16 B.5-6 17 A.3-3 16 B.2-1 16 B.5-7 17 A.3-4 16 B.2-2 16 B.5-8 17 A.3-5 16 B.2-3 16 B.5-9 17 A.3-6 16 B.5-10 17 A.3-7 16 B.3-1 16 b.5-11 17 B.3-2 16 B.5-12 17 A.4 1 16 B.5-3 16 A.4-2 16 B.3-4 16 B.6-1 17 A.4-3 16 B.3-5 16 B.6-2 17 A.4-4 16 B.3-6 16 B.6-3 16 A.4-5 16 B.3-7 16 B.3-8 B.7-1 O'

A.5-1 16 B.3-9 16 16 B.7-2 16 16 A.5-2 16 B.3-10 16 B.7-3 16 A.5-3 16 B.3-11 16 B.7-4 16 A.5-4 16 B.3-12 16 B.7-5 16 A.5-5 16 B.3-13 16 B.7-6 16 A.5-6 16 B.3-14 16 B.7-7 16 A.5-7 16 B.3-15 16 B.7-8 16 A.5-8 16 B.3-16 16 B.7-9 16 A.5-9 16 B.3-17 16 B.7-10 16 A.5-10 16 B.3-18 16 B.7-11 16 B.3-19 16 B.7-12 16 B.1-0 16 B.3-20 16 B.7-13 16 B.1-1 17 B.3-21 16 B.7-14 16 B.1-2 17 B.3-22 16 B.7-15 16 B.1-3 16 B.3-23 16 B.7-16 16 B.1-4 16 B.3-24 16 B.7 17 16 B.1-5 16 B.3-25 16 B.7-18 16 B.1-6 16 B.3-26 16 B.7-19 16 B.1-7 16 B.3-27 16 B.7-20 16 B.1-8 16 B.3-28 16 B.7-21 16 B.1-9 16 B.3-29 16 B.7-22 16 B.1-10 16 B.3-30 16 B.7-23 16 B.1-11 16 B.3-31 16 B.7-24 16 B.1-12 16 B.7-25 16 B.1-13 17 B.4-1 17 B.7-26 16 B.1-14 B.4-2 B.7-27 O B.1-15 17 17 B.4-3 17 16 B.7-28 16 16 Page 1 ODCM Rev. 18

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LIST OF EFFECTIVE PAGES PAGE EEL. FAGE E F. AGE EEL-B.7-29 16 B-1 16 X-B. 2-1 thru B.7-30 16 B-2 16 X-B.2-3 18 B.7-31 16 3-3 16 B.7-32 16 B-4 16 X-B.3-1 thru B.7-33 16 B-5 16 X-B.3-31 18 B.7-34 16 B-6 16 B.7-35 16 B-7 16 X-B.4-1 thru B.7-36 16 B-8 16 X-B.4-10 18 B.7-37 16 B-9 16 a.7-38 16 B-10 16 X-B.5-1 thru B.7-39 16 B-11 16 X-B.5-12 18 B.7-40 16 C-1 16 X.B.6-1 thru B.8-1 17 C-2 16 X-B.6-3 18 B.8-2 17 C-3 16 B.8-3 17 C-4 16 X-B.7-1 thru B.8-4 17 C-5 16 X-B.7-40 18 B.8-5 16 C-6 16 B.8-6 16 X-B.8-1 thru B.8-7 16 TOC X-1 thru X-B.8-19 18 B.8-8 16 X-9 18 B.8-9 16 X-R-1 18 B.8-10 16 Abstract X-1 18 B.8-11 16 Y-1 thru B.8-12 16 X-A.1-1 18 Y-11 18 B.8-13 16 B.8-14 16 X-A.2-1 18 B.8-15 16 B.8-16 16 X-A.3-1 and B.8-17 16 X-A.3-2 18 B.8-18 16 B.8-19 16 X-A.4-1 and X-A.4-2 18 R-1 16 X-A.5-1 thru A-1 16 X-A.5-10 18 A-2 16 A-3 16 X-A.6-1 thru A-4 16 X-A.6-11 18 A-5 16 A-6 16 X-A.7-1 thru A-7 16 X-A.7-12 18 A-8 16 A-9 16 X-A.8-1 and j A-10 16 X-A.8-2 18 A-11 16 A-12 16 X-A.9-1 thru A-13 16 X-A.9-13 18 A-14 16 A-15 16 X-A.10-1 thru A-16 16 X-A.10-3 18 A-17 16 A-18 16 X-B.1-0 thru A-19 16 X-B.1-28 18 Page 2 ODCM Rev. 18 l

PART A RADIO 1DGICAL EFFLUENT MONITORING PROGRAMS

1.0 INTRODUCTION

The purpose of Part A of the ODCM (Off-Site Dose Calculation Manual) is to

! describe the sampling and analysis programs conducted by the Station, which provide l

input to the models in Part B for calculating liquid and gaseous effluent concentrations, monitor setpoints, and off-site dosos. The results of Part B calculations are used to determine compliance with the concentration and dose requirements of Technical Specification 3/4.11.

The Radiological Environmental Monitoring Program required as a minimum to be conducted (per Technical Specification 3/4.12) is described in Part A, with the identification of current locations of sampling stations being utilized to meet the

program requirements listed in Part B. The information obrained from the conduct of l

the Radiological Environmental Monitorin8 Program provides data on measurable levels of radiation and radioactive materials in the environment necessary to evaluate the relationship between quantities of radioactive materials released in effluents and resultant radiation doses to individuals from principal pathways of exposure. The

! data developed in the surveillance and monitoring programs described in Part A to

! the ODCM provide a means to confirm that measurable concentrations of radioactive materials released as a result of Seabrook Station operations are not significantly higher than expected based on the dose models in Part B.

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V A.1-1 ODCM Rev. 16 l

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1 2.0 RESPONSIBILITIES FOR PART A All changes to Part A of the ODCM shall be reviewed and approved by the O prior to implementation. Station Operation Review Cosmaittee (SORC) and the l It shall be the responsibility of the Station Director to ensure that the ODCK is used in the performance of the surveillance requirements and administrative controls of the appropriate portions of the Technical Specifications. I i

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O A.2-1 ODCM Rev. 16

3.0 LIOUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table A 3-1 for Seabrook Unit 1. The results of the V radioactive analysis shall be used as appropriate with the methodology of Part B of the ODCM to assure that the concentrations of liquid effluents at the point of release from the multiport diffuser of the Circulating Water System are maintained within the limits of Technical Specification 3.11.1.1 for Unit 1.

Radioactive effluent information for liquids obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part B to damonstrate compliance with the dose objectives and surveillance requirements of Technical Specifications 3/4.11.1.2, 3/4.11.1.3, and 3/4.11.4 O

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TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

{O Notations m The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 sb E x V x 2.22 x 10' x Y x exp (-AAt)

Where:

LLD - the "a priori" lower limit of detection (microcurie per unit mass or volume),

s3

- the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E - the counting efficiency (counts per disintegration),

V - the sample size (units of mass or volume),

2.22 x 105 - the number of disintegrations per minute per microcurie, Y - the fractional radiochemical yield, when appli.able, A - the radioactive decay constant for the particular radionuclide (s-1) , and At - the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and At shculd be used in the calculation.

It should be recognized that the LLD is defined as an a griori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular measurement.

m A batch release is the discharge of liquid wastes of a dLerete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

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A.3-5 ODCM Rev. 16 j l

TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Notations (Continued)

(8) The principal gamma emitters for which the LLD specification applies inclurie the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only e ase nuclides are to be considered. Other gamma peaks that are identifiabb, together with those of the above nuclides, shall also be analyzed and reported l

in the Annual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4. Isotopes which are not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations.

(') A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(8) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g. , from a volume of a system that has an input flow during the continuous release.

(8) Sampling and analysis is only required when Steam Cenerator Blowdown is directed to ths discharge transition structure.

(7) Principal gamma emitters shall be analyzed weekly in Service Water. Sample and analysis requirements for dissolved and entrained gases, tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gamma emitters exceeds the LLD.

The following are additional sampling and analysis requirements:

a. PCCW sampled and analyzed weekly for principal gamma emitters.

b. Sample Service Water System (SWS) daily for principal gamma emitters whenever primary component cooling water (PCCW) activity exceeds 1x10-8 uC/ce.

c. With the PCCW System radiation monitor inoperable, sample PCCW and SWS daily for principal gamma emitters.

d. With a confirmed PCCW/SWS leak and PCCJ activity in excess of lx10-'

uC/ce, sample SWS every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for principal gamma emitters. ;

t

e. The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity to detect a PCCW/SWS leak is equal to or greater than that of an SWS radiation monitor, located in the unit's combined SWS discharge, with an LLD of 1x10-s uC/cc. If this sensitivity cannot be achieved, the SWS will be sampled once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(a) If the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be sampled and analyzed for Iodine-131 and principal gamma emitters prior to release.

A.3-6 ODCM Rev. 16

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TABLE A.3 1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Notations (Continued) m Quarterly composite analysis requirements shall only be required when analysis for principal gamma emitters indicate positive radioactivity.

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A.3-7 ODCM Rev. 16

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4.0 GASEOUS EFFillENT SAMPLING AND ANALYSIS PROGRAM Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table A.4-1 for Seabrook Unit 1. The results of the N radioactive analyses shall be used as appropriate with the methodologies of Part B of the ODCM to assure that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary are within the limits of Technical Specification 3.11.2.1 for Unit 1.

Radioactive effluent information for gaseous wastes obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part B to demonstrate compliance with the dose objectives and surveillance requirements of Technical Specifications 3/4.11.2.2, 3/4.11.2.3, 3/4.11.2.4, and 3/4.11.4.

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TABLE A.4-1 RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l l

(Continued)

O Notations m The 1.LD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detered with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 sd LLD - E x V x 2.22 x 106 x Y x exp (-Aat)

Where:

LLD - the "a priori" lower limit of detection (microcurie per unit mass or volume),

sd

- the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E - the counting efficiency (counts per disintegration),

V - the sampic size (units of mass or volume),

2.22 x 108 - the number of disintegrations per minute per microcurie, Y - the fractional radiochemical yield, when applicable, A - the radioactive decay constant for the particular radionuclide (s-1) , and At - the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.

O A 4-4 ODCM Rev. 16

TABLE A.4-1 RADIOACTIVE CASEOUS UASTE SAMPLING AND ANALYSIS PROGRAM (Continued)

Notations (Continued)

(2) The principal gamma emitters for which the LLD specification applies include i the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble 5as releases and Mn-54, Fe-59, co-58, C2-60 Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Co-144 in iodine and particulate releases.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, l shall also be analyzed and reported in the annual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4. Isotopes which are not detected should be reported as "not detected." Valu~es determined to be below detectable levels are not used in dose calculations.

(8) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unless; 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a factor of 3; 2) the noble gas activity monitor for the plant vent has not increased by more than a factor of 3. For containment purge, requirements apply only when purge is in operation.

") Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

O The ratio of the sample flow rate to the sampled stream flow rate shall be Q ")

known for the time period covered by each dose or dose rate calculation made in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3. l

") Samples shall be changed at least once per seven (7) days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least seven (7) days following each shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED UIERNAL POWER within a one-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

") Samples shall be taken prior to start-up of condenser air removal system when there have been indications of a primary to secondary leak.

") Quarterly composite analysis requirements shall only be required when analysis for principal gamma emitters indicate positive radioactivity.

O A.4-5 ODCM Rev. 16

1 l

l 5.0 RADIOIDGICAL ENVIRONMENTAL MONITORING 5.1 SAMPLING AND ANALYSIS PROGRAM The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of members of the public resulting from station operation. This monitoring program is required by Technical Specification 3.12.1. The monitoring program implementsSection IV.B.2 of Appendix I to 10CFR, Part 50, and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways which have been incorporated into Part B of the ODCM.

The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this per'iod, program changes may be initiated based on operational experience.

In accordance with Technical Specification surveillance requirements, 4.12.1, sampling and analyses shall be conducted as specified in Table A.5-1 for locations shown in Section 4 of Part B to the ODCM. Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown ,

I on Tables A.5-2 and A.5-3, respectively.

It should be noted that Technical Specification 3.12.1.C requires that if milk or fresh leafy vegetable samples are unavailable from one or more sample locations required by the REMP, new specific locations for obtaining replacement samples (if available) shall be added to the REMP within 30 days, and the specific locations n from which the samples are unavailable may then be deleted from the monitoring

(- program. In this context, the term unavailable means that samples are no longer available to be collected now or in the future for reasons such as the permission from the owner to collect the samples has baen withdrawn or he has gone out of business, thus causing the permanent loss of the sample location.

5.2 IAND USE CENSUS As part of the Radiological Environmental Monitoring Program, Technical I Specification 3/4.12.2 requires that a land use census be conducted annually during growing season to identify within a distance of 8 km the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 producing broad leaf vegetation.

The land use census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modifications to the monitoring program and dose assessment models are made, if necessary. This census satisfies the requirements of Section IV.3.3 of Appendix I to 10CFR Part 50.

For the purpose of conducting the land use census as required by Technical Specification 4.12.2, station personnel should determine what survey methods will provide the necessary results considering the type of information to be collected and the use to which it will be put, such as the location of potential milk animal pathway for use in routine dose calculations. Land use census results shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., roadside identification of locations), aerial surveys, or by consulting local agricultural authorities.

O A.5-1 ODCM Rev. 16

5.2 IAND USE CENSUS (Continu2d)

Technical Specification 3.12.2.b requires that new locations identified from the census that yield a calculated dose of dose commitment 20 percent greater than at a location from which samples are currently being obtained be added within 30 days to the REKP. These new locations required to be added to the sampling program shall only be those from which permission from the owner to collect samples can be cbtained and sufficient sample volume is available.

O O

A.5-2 ODCM Rev. 16

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TABLE A.5-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa.Os (Continued)

Table Notation

c. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b. The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s3 E V 2.22 Y exp (-AAt)

Where:

LLD is the "a prioria lower limit of detection as defined above, as picoeuries per unit mass or volume; 4.66 is a constant derived from the K.g. and K 3,s values for the 95%

confidence level; s3 is the standard deviation of the background counting rate or of the countinF rate of a blank sample as appropriate, as counts per minute; E is the counting efficiency, as counts per disintegration; V is the sar.ple size in units of mass or volume; 2.22 is the number of disintegrations per minute per picoeurie; Y is the fractional radiochemical yield, when applicable; A is the radioactive decay constant for the particular radionuclide as per second; and At for environmental samples is the elapsed time between sample collection and time of counting, as seconds.

Typical values of E, V, Y, and at should be used in the calculation.

In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g. , Potassium-40 in milk samples).

O A.5-8 ODCM Rev. 16

TABLE A.5-2 DETECTION CAPABILITIES FOR ENVIDANNENTAL SAMPLE ANALYSISa.f.s '

(Continued) i O Table Notation l (Continued)

It should be recognized that the LLD is defined as an a oriori (before the ' l fact) limit representing the capability of a measurement system and not as an A nosteriori (after the fact) limit for a particuler measurement. This does l

not preclude the calculation of an a nosteriori LLD for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters such as decay while sampling and during analysis. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs l

unschievable. In such cases, the contributing factors shall be identified and ;

described in the Annual Radiological Environmental Operating Report, j l

c. Parent only.

d. The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an eight-day period following collection. The calculation shall be predicated on the nonnal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an insignificant amount (at least 3.6% of its original value). Th3 ingrowth equations will assume that the supported La-140 activity at the time of collection is zero,

e. Broad leaf vegetation only,

f. If the measured concentration minus the three standard deviation uncertainty is found to exceed the specified LLD, the sample does not have to be analyzed to meet the specified LLD.

g. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with recommendations of Regulatory Guide 4.13, Revision 1, July 1977.

O A.5-9 ODCM Rev. 16

6 O

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SEABROOK STATION ODCM PART B RADIOIDGICAL CALCULATIONAL METHODS AND PARAMETERS O

l l

O B.1-0 ODCM Rev. 16

l

1.0 INTRODUCTION

Part B of the ODCM (Off-Site Dose Calculation Manual) provides formal and approved methods for the calculation of off-site concentration, off-site doses and O- effluent monitor setpoints, and indicates the locations of environmental monitoring stations in order to comply with the Seabrook Station Radiological Effluent Technical Specifications (RETS), Sections 3/4.3.3.9, 3/4.3.3.10, and 3/4.11, as well as the REMP detailed in Part A of the manual. The ODCM forms the basis for station procedures which document the off-site doses due to station operation which are used to show compliance with the numerical guides for design objectives of Section II of Appendix I to 10CFR Part 50. The mathods contained herein follow accepted NRC guidance, unless otherwise noted in the text.

The references to 10 CFR Part 20 in Part B of the ODCM refer to revisions of 10 CFR Part 20 published prior to 1 January 1993. The decision to continue the use of the "old" version of 10 CFR Part 20 is based on an NRC letter dated June 30, 1993, from Thomas E. Murley to Thomas E. Tipton. For the convenience of the plant staff a copy of 10 CFR Part 20 (Rev.1 January 1992) has been included in Appendix B.

1.1 RESPONSIBILITIES FOR PART B All changes to Part B of the ODCM shall be reviewed and approved by the ,

Station Operation Review Committee (SORC) in accordance with Technical Specification l ]

6.13 prior to implementation. Changes made to Part B shall be submitted to the Commission for their information in the Annual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

It shall be the responsibility of the Station Director to ensure that the ODCM is used in the performant:e of in-plant surveillance requirements and administrative l

controls of the appropriate portions of the Technical Specifications, and Effluent l

Control Program detailed in Part A of the manual. The Executive Director of Nuclear

! Production shall be responsible to ensure that the Radiological Environmental l Monitoring Program described in Section 4 of Part B is implamented in accordance l with Technical Specification 3/4.12 and Part A of this manual.

In addition to off-site dose calculations for the demonstration of compliance with Technical Specification dose limits at and beyond the site boundary, l

10CFR20.1302 requires that compliance with the dose limits for individual members of the public (100 aren/yr total effective dose equivalent) be demonstrated in l

controlled areas on-site. Demonstration of compliance with the dose limits to members of the public in controlled areas is implemented per Health Physics Department Procedures, and is outside the scope of the ODCM. However, calculations performed in accordance with the ODCM -an be used as one indicator of the need to perform an assessment of exposure to members of the public within the site boundary.

Since external direct exposure pathways are already subject to routine exposure rate surveys and measurements, only the inhalation pathway need be assessed. The accumulated critical organ dose at the site boundary, as calculated per ODCt!

l Sections 3.9 and 3.11, can be used as an indicator of when additional assessments of on-site exposure to members of the public is advisable (see Section 3.11.2).

Off-site critical organ doses from station effluents should not, however, be the only indicator of potential on-site doses.

O B.1-1 ODCM Rev. 17 l

l

1.2

SUMMARY

OF METHODS, DOSE FACTORS, I.IMITS, CONSTANTS, VARIABLES AND

DEFINITIONS This section summarizes the Method I dose equations which are used as the primary means of demonstrating compliance with RETS. The concentration and setpoint methods are identified in Table B.1-2 through Table B.1-7. Appendix C provides documentation for an alternate computerized option, designated as Method IA in the ODCM, for calculating doses necessary to demonstrate compliance with RETS. The Effluent Management System (EMS) software psclange used for this purpose is provided by Canberra Industries, Inc. Where more refined dose calculations are needed, the use of Method II dose determinations are described in Sections 3.2 through 3.9 and 3.11. The dose factors used in the equations are in Tables B.1-10 through B.1-14 cnd the Regulatory Limita are summarized in Table B.1-1.

The variables 'and special definitions used in this ODCM, Part B, are in Tables B.1-8 and B.1-9.

l l

B.1-2 ODCM Rev. 17

6 1

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TABLE B.1-2

SUMMARY

OF METHOD I EOUATIONS TO CALCUIATE UNRESTRICTED AREA LIOUID CONCENTRATIONS Equation Number Category Equation f

i 2-1 Total Fraction of MPC in Liquids, Except Noble Cases FN. { si f 2-2 Total Activity of Dissolved and Entrained Noble Cases

= { CIG 2

from all Station Sources Cf

'5 2E-04 O

B.1-6 ODCM Rev. 16

l TABLE B.1-3

SUMMARY

OF METHOD I EOUATIONS TO CALCUTATE OFF-SITE DOSES MtOM LIOUID #FTRASES Equation

' Nn=her Caterorv Eauntion 3-1 Total Body Dose Dtb("Y'")

N i 9 i UE itb 3-2 Maximum Organ Dose D,,(arem) - k Qg DEg ,,

O O B.1-7 ODCM Rev. 16 l

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y ai -

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t rmat ed a Co a t e r ,l it C oFmu S a t uc - v nii f e eatt fl s gi r OE orra DOTP - -

S 0E

b C l l l l l l

TABLE B.1-7

SUMMARY

OF METHODS FOR 3.EIPOINT DETERMINATIONS Number Categorv Ecuation 5-1 Liould Effluents:

Liquid Waste Test Fa.

Tank Monitor R setpoint (M )~ fl F, X DF"I" E C1 7

1 (RM-6509) 5-23 PCCW Rate-of- 8 ,_1._

Change Alarm RCset(gph) - 1x10 SUF Gaseous Effluents:

Plant Vent Wide Range Cas Monitors (RM-6528-1, 2, 3) 5-5 Total Body R - 588 tb (pCi/sec) DFB 5-6 Skin R skin 1 (pCi/sec) - 3000 DF' c

O O

B.1-14 ODCM Rev. 17 i

TABLE B.1-8

SUMMARY

OF VARTABLES t'

! Units Variable Definition

- Concentration at point of discharge and pCi/ml C ,u entrained noble gas "i" in liquid pathways from all station sources

- Total activity of all dissolved and pCi Cf entrained noble gases in liquid pathways "I from all station sources Cai

- Concentration of radionuclide "i" et the pCi point of liquid discharge al Ci - Concentration of radionuclide "1" pCi/ml C,i - Concentration, exclusive of noble gases, of uCi radionuclide "i" from tank "p" at point of "I discharge C3 - Concentration of radionuclide "i" in pCi/ml l

mixture at the monitor

- Off-site beta dose to air due to noble mrad D{irt.) gases in elevated release

- Off-site beta dose to air due to noble gas mrad D{irts) in ground level release .

- Beta dose to air at Science & Nature Centar mrad i D{ irs (.) due to noble gases in elevated release (

- Beta dose to air at Science & Nature Center mrad D{irz(s) due to noble gases in ground level release

- Beta dose to air at " Rocks" due to noble mrad D$ trac.) gases in elevated release

- Beta dose to air at " Rocks" due to noble mrad D{tra(s) gases in ground level release

- Off-site gamma dose to air due to noble mrad Dltr<.) gases in elevated release

- Off-site gamma dose to air due to noble mrad D!irts) gases in ground level release

- Gamma dose to air at Science & Nature mrad DIirsc.) Center due to noble gases in elevated releasc

- Gamma dose to air at Science & Nature mrad D!irz(s) Center due to noble gases in ground level release

- Camaa dose to air at " Rocks" due to noble mrad O Djirac.) gases in elevated release B.1-15 ODCM Rev. 17

TABLE B.1-8

SUMMARY

OF VARIABLES (Continued)

O Variable Definition Units

- Gamma dose to air at " Rocks" cue to noble mrad D!1ac,3 gases in ground level release D c,3 - Critical organ dose from an elevated mrem release to an off-site receptor D c.) - Critical organ dose from a ground level mrem release to an off-site receptor D,gc.3 - Critical organ dose from an elevated mrem release to a receptor at the Science &

Nature Center De gc,3 - Critical organ dose from a ground level mrem release to a receptor at the Science &

Nature Center D,gc.) - Critical organ dose from an elevated mrem release to a receptor at the " Rocks" De ac,3 - Critical organ dose from a ground level mrem release to a receptor at the " Rocks" Da - Direct done mrem

- Canua dose to air, corrected for finite mrad I D2init. cloud l D. - Dose to the maximum organ mrem ,

1 D8 - Dose to skin from beta and gamma mrem '

Du, - Dose to the total body mrem l DFe, - Minimum required dilution factor ratio

- Composite skin dose factor for off-site mrem-sec/ Ci-yr DF i receptor

- Composite skin dose factor for Science & mrem-sec/pci-yr DFiz Nature Center

- Composite skin dose factor for the " Rocks" mrem-sec/ Ci-yr DFig DFB i - Total body gamma dose factor for nuclide !

"i" (Table B.1-10) arem3 )

pCi-yr l DFB, - Composite total body dose factor mrem3 pCi yr O

I B.1-16 ODCM Rev. 17 l 1

TABLE B.1-8

SUMMARY

OF VARIABLES (Continued)

O V

Variable Definition Units DFLi u, - Site-specific, total body dose factor for a liquid release of nuclide "i" (Table B.1-11)

W DFLw - Site-specific, maximum organ dose factor "#**

for a liquid release of nuclide "i" (Table B.1-11) N DFBi .c.3 - Site-specific, critical organ dose factor arem/pci for an elevated gaseous release o~f nuclide "i" (Table B.1-12)

DFGie.c,3 - Site-specific critical organ dose factor arem/pCi for a ground level release of nuclide "i" (Table 3.1-12)

DFGi .gg.3 - Science & Nature Center-specific critical arem/pci organ dose factor for an elevated release of nuclide "i" (Table B.1 14)

DFGi ,g(,3 - Science & Nature Center-specific critical arem/pci organ dose factor for a ground level release of nuclide "i" (Table B.1-14) }

DFG 1 coat.) - The " Rocks"-specific critical organ dose arem/pci ?

\ factor for an elevated release of nuclide "i" (Table B.1-15)

DFGieon(s)

- The " Rocks" specific critical dose factor mrem /pci for a ground level release of nuclide "i" (Table B.1-15)

- Site-specific critical organ dose rate arem-sec DFG icot.) factor for an elevated gaseous release of pci-yr nuclida "i" (Table B.1-12)

- Site-specific critical organ dose rate arem-see DFGt ..cs) factor for a ground level release of Ci-yr nuclide "i" (Table B.1-12)

- Science & Nature Center-specific critical arem-sec DFG ic e<.) organ dose rate factor for an elevated release of nuclide "i" (Table B.1-14) FCi-7#

- Science & Nature Center-specific critical arem-see DFG icats) organ dose rate factor'for a ground level pci-yr release of nuclide "i" (Table B.1-14)

- The " Rocks"-specific critical organ dose arem-sec DFG icoac.) rate factor for an elevated release of pci-yr nuclide "i" (Table B.1-15)

O B.1-17 ODCM Rev. 16 I

1 a

TABLE B.1-8

UMMARY OF VARIABLES (Continued)

Definition Units O

Variable

- The " Rocks"-specific critical organ dose mrem-sec DFG icon (s) rate factor for a ground level release of #Ci-F nuclide "i" (Table B.1-15)

DFS i - Beta skin dose factor for nuclide "i" mrem-m 8 (Table B.1-10) pCL-yr DF's - Combined skin dose factor for nuclide "i" mrem-m8 (Table B.1-10) pCi-yr

- Ganna air dose factor for nuclide "i" mrad-m8 DFi (Table B.1-10) pGi-yr

- Beta air dose factor for nuclide "i" mrad-m8 Dd (Table B.1-10) pCi-yr

- Critical organ dose rate to an off-site "#**

D eote) receptor due to elevated release of F iodines, tritium, and particulates

- Critical organ dose rate to an off-site "#**

Deo(s) receptor due to ground level release of F iodines, tritium, and particulates

- Critical organ dose rate to a receptor at Doorte) the Science & Nature Center due to an M elevated release of iodines, tritium, and F particulates

- Critical organ dose rate to a receptor at "#**

Deer(s) the Science & Nature Center due to a ground 1evel release of iodines, tritium, and F particulates

- Critical organ dose rate to a receptor at "#**

Deonce) the " Rocks" due to an elevated release of F iodinas, tritium, and particulates

- Critical organ dose rate to a receptor at "#8" D coR(s) the " Rocks" due to a ground level release of iodines, tritium, and particulates F

- Skin dose rate to an off-site receptor due D atint.) to noble gases in an elevated release yr

{

j l

)

f 9

B.1-18 ODCM Rev. 16

_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - - - _ - _ - _ - _ _ _ _ __ a

l TABLE B.1-8

SUMMARY

OF VARIABLES

, (Continued)

( )

Variable Definition Units

- Skin dose rate to an off-site receptor due D*ints) to noble gases in a ground level release yr )

- Skin dose rate to a receptor at the Science

"#8" DninEce) & Nature Center due to noble gases in an elevated release F

- Skin dose rate to a receptor at the Science Deinz(s) & Nature Center due to noble gases in a ground level release F

- Skin dose rate to a receptor at the " Rocks" Deinnte) due to noble gases in an elevated release yr

- Skin dose rate to a receptor at the " Rocks" Dainnts) due to noble gases in a ground level release F

- Total body dose rate to an off-site "#8" Dtb(e) receptor due to noble gases in an elevated release F N

[h Total body dose rate to an off-site mrem j Deb (s) receptor due to noble gases in a ground level release F l

- Total body dose rate to a receptor at the D tbE(e) Science & Nature Center due to noble gases in an elevated release F

- Total body dose rate to a receptor at the mrem b tbE(s) Science & Nature Center due to noble gases in a ground level release F

- Total body dose rate to a receptor at the Dthate) " Rocks" due to noble gases in an elevated release F

- Total body dose rate to a receptor at the Dtbn(s) " Rocks" due to noble gases in a ground 1evel release F D/Q - Deposition factor for dry deposition of elemental radioiodines and other particulates E l Fa - actual or estimated flow rate out of gpm or ft /sec 3

discharge tunnel O

B.1-19 ODCM Rev. 17

TABLE B.1-8

SUMMARY

OF VARIABLES (Continued)

O Vari able Definition Units F, - Flow rate past liquid waste test tank gpm monitor F. - Maximum allowable discharge flow rate from gpm liquid test tanks F - Flow rate past plant vent monitor f;f;f; 2 2 3

- Fraction of total MFC associated with Paths Dimensionless f4 1, 2, 3, and 4

- Total fraction of MFC in liquid pathways Dimensionless

@ (excluding noble gases)

MPCs

- Maximum permissible concentration for pCi radionuclide "i" (10CFR20, Appendix B, Table 2, Column 2) cc Qi - Release to the environment for radionuclide curies, or "i" peuries

- Release rate to the environment for yCi/sec Di radionuclide'"i" R,.sptos - Liquid monitor response for the limiting pCi/ml concentration at the point of discharge Rm, - Response of the noble gas monitor to epm, or pCi/see limiting total body dose rate Ro - Response of the noble gas monitor to cpm, or pCi/sec limiting total body dose rate Sr - Shielding factor Dimensionless S - Detector counting efficiency from the gas monitor calibracion CP" or mR/hr pCL-cc pGijcc S,1 - Detector counting efficiency for noble gas cpm

.i. or mR/hr pCi-cc pCijcc S1

- Detector counting efficiency from the l liquid monitor calibration cps pCi/ml l

Su - Detector counting efficiency for cps radionuclide "i" 1 pCi/ml

]

O B.1-20 ODCM Rev. 17

TABLE B.1-8

SUMMARY

OF VARIABLES (Continued)

[

V)

Variable Definition Units X/Q -

Average long-term undepleted atmospheric dispersion factor (Tables B 7-4, B.7-5, and sec m,

B.7-6)

(X/Q)7 -

Effective long-term average gamma atmospheric dispersion factor sec (Tables B.7-4, B.7-5, and B.7-6) m, SWF -

Service Water System flow rate -

gph PCC -

Primary compenent cooling water measured pCi/ml (decay corrected) gross radioactivity concentration t-" -

Unitiess factor which adjusts the value of Dimensionless atmospheric dispersion factors for elevated or ground-level releases with a total release duration of t hours s

i i

C' i

N.

B.1-21 ODCM Rev. 17 i J

TABLE B.1-9 DEFINITION OF TERMS Critical Receptor - A hypothetical or real individual whose location and behavior cause him or her to receive a dose greater than any other possible real individual.

D9.33 - As used in Regulatory Guide 1.109, the term " dose," when applied to individuals, is used instead of the more precise term " dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition er radioactivity, the term " dose,"

as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. The dose is measured in mrem to tissue or arad to air.

Dose Rate - The rate for a specific averaging time (i.e., exposure period) of dose accumulation.

Liould Radwaste Treatment System - The components or subsystems which comprise the available treatment system as shown in Figure B.6-1.

O j

)

J l

Q B.1-22 ODCM Rev. 17

6 O ro m it r

Ac ad a i 3

r y

- 353532224443333 000000000000000 1

v e

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T E

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a S r vi -

no m i 000000000000000 e C dt o IP r P n - - - - - - - - - - - - - - -

u EEEEEEEEEEEEEEE ecde na uansm g 233515755209983 239321633149526 R

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0 TA 1 T S r e s e 3

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no a e r 2 B K if y -

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- 253322224343322 En Lna S r l ortes emr Cp i 000000000000000

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b a 112111225153311 R

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,l

i

\

TABLE B.1-11 DOSE FACTORS SPECIFIC FOR SEABROOK STATION >

EQB O.

LIOUID REL2ASES Total Body Maximum Organ Dose Factor Dose Factor I DEtta ( ci I "#Li "* I c E.adionuclide H-3 3.02E-13 3.02E-13 Na-24 1.38E-10 1.42E-10 Cr-51 1.83E-11 1.48E-09 Mn-54 5.15E-09 2.68E-08 Fe-55 1.26E-08 - 7.67E-08 Fe-59 8.74E-08 6.66E-07 Co-58 2.46E-09 1.40E-08 Co-60 6.15E-08 9.22E-08 2n-65 2.73E-07 5.49E-07 Br-83 1.30E-14 1.89E-14 Rb-86 4.18E-10 6.96E-10 Sr-89 2.17E-10 7.59E-09 Sr-90 3.22E-08 1.31E-07 Nb-95 5.25E-10 1.58E-06 Mo-99 3.72E-11 2.67E-10 Tc-99m 5.22E-13 1.95E-12 Ag-110m 1.01E-08 6.40E-07 Sb-124 1.71E-09 9.89E 09 Sb 125 6.28E-09 8.31E-09 1 Te-127m 7.07E-08 1.81E-06 Te-127 3.53E-10 9.54E-08 Te-129m 1.54E-07 3.46E 06 Te-129 7.02E-14 1.05E-13 Te-131m 3.16E-08 2.94E 06 Te-132 9.06E-08 3.80E-06 I-130 2.75E-11 3.17E 09 I-131 2.30E-10 1.00E-07 I I-132 6.28E-11 6.36E-11 1-133 3.85E-11 1.15E-08 l I-134 1.19E-12 1.41E-12 l

I-135 5.33E-11 4.69E-10 i Cs-134 3.24E-08 3.56E-08 Cs-136 2.47E-09 3.27E-09 f 3.58E-08 4.03E-08 Cs-137 Ba-140 1. 70E-10 3.49E-09 La-140 1.07E-10 4.14E-08 Ce-141 3.85C-11 9.31E-09 ,

j Ce-144 1.96E-10 6.46E-08 Other* 3.12E-08 1.58E-06*

O Dose factors to be used in Method I calculation for any "other" detected gamma emitting radionuclide khich is not included in the above list.

I B.1-24 ODCM Rev. 16 }

I

TABLE B.1-12 DOSE AND DOSE RATE FACTORS SPECIFIC FOR SEABROOK STATION IDE IODINES. TRITIUM AND PARTICUIATE RELEASES Critical Organ Critical Organ Critical Organ Dose Critical Organ Dose Factor Dose Factor for Rate Factor for Dose Rate Factor for Elevated Ground 14 vel Elevated Release for Ground Level Release Point Release Point Point Release Point

,nad,fo; on-., gg> om-., gg) o m:-<., < ;; p om:..., < ;;p H-3 3.08E-10 3.76E-09 9.71E-03 1.19E-01 Cr-51 8.28E-09 2.89E-08 2.91E-01 1.01E+00 Mn-54 1.11E-06 3.79E-06 4.38EF01 1.50E+02 ,

Fe 59 1.06E-06 3.65E-06 3.53E+01 1.21E+02 Co-58 5.56E-07 1.91E-06 2.00E+01 6.88E+01 Co 60 1.21E-05 4.12E-05 5.42E+02 1.85E+03 Zn 65 2.33E-06 7.93E-06 7.82E+01 2.66E+02 Sr-89 1.98E-05 6.73E-05 6.24E+02 2.12E+03 Sr-90 7.21E-04 2.47E-03 2.27E+04 7.79E+04 Zr-95 1.10E-06 3.77E-06 3.63E+01 1.24E+02 Nb 95 2.01E-06 6.86E-06 6.40E+01 2.20E+02 l D

h Mo-99 1.63E-08 1.10E-07 1.04E-05 5.39E-01 9.62E+01 3.56E+00 3.31E+02 l

Ru-103 3.03E-06 Ag-110m 5.02E-06 1.72E-05 1.80E+02 6.15E+02 Sb-124 1.83E-06 6.28E-06 6.15E+01 2.11E+02 I-131 1.47E-04 5.04E-04 4.64E+03 1.59E+04 I-133 1.45E-06 5.72E-06 4.57E+02 1.80E+02 Cs-134 5.C2E-05 1.91E-04 1.81E+03 6.18E+03 Cs-137 5.47E-05 1.86E-04 1.79E+03 6.09E+03 Ba-140 1.55E-07 6.39E-07 5.01E+00 2.06E+01 Ce-141 2.65E-07 9.28E-07 8.45E+00 2.96E+01 Ce-144 6.09E-06 2.09E-05 1.93E+02 6.62E+02 Other* 4.09E-06 1.39E-05 1.29E+02 4.38E+02

Dose factors to be used in Method I calculations for any "other" detected gassa emitting radionuclide which is not included in the above list.

O B.1-25 ODCM Rev. 16

i TABLE B.1-13 COMBINED SKIN DOSE RATE FACTORS SPECIFIC FOR SEABROOK STATION SPECIAL RECEPTORS (1) FOR NOBLE CAS RELEASE Science & Nature O

Science & Nature Center Center The " Rocks" Combined Skin Combined Skin The " Rocks" Combined Skin Dose Rate Factor Dose Rate Factor Combined Skin Dose Rate Factor for Elevated for Dose Rate Factor for Release Ground Level for Elevated Ground Level Releaso Point Release Point Release Point Point Radio- pr **> ( mem-sec ) ( arem-sec ppe ( mem-sec) DF'mW ( mem-sec)

DF'** pci-yr 's e

*8 pci-yr pei-yr pci-yr nuclide Ar-41 1.57E-02 1.17E-01 9.73E-02 6.99E-01 Kr-83m 2.35E-05 1.13E-04 1.07E-04 5.58E-04 Kr-85m 3.84E-03 4.08E-02 3.16E-02 2.69E-01 Kr-85 2.16E-03 3.09E-02 2.29E-02 2.15E-01 Kr-87 2.31E-02 2.60E-01 2.00E-01 1.74E+00 Kr-88 2.23E-02 1.44E-01 1.25E-01 8.18E-01 Kr-89 3.73E-02 3.34E-01 2.68E-01 2.12E+00 Kr-90 3.15E 02 2.64E-01 2.14E-01 1.64E+00 ;

Xe-131m 9.52E-04 1.19E-02 8.96E-03 8.07E-02 Xe-133m 1.99E-03 2.48E-02 1.87E-02 1.68E-01 Xe-133 9.20E-04 9.11E-03 7.16E-03 5.92E-02 Xe-135m 5.24E-03 3.61E-02 3.07E 02 2.11E-01 Xe-135 5.32E-03 5.41E-02 4.23E-02 3.53E-01 Xe-137 2.14E-02 2.89E-01 2.16E-01 2.00E+00 Xe-138 1.78E-02 1.49E-01 1.21E-01 9.27E-01 l

l (1) See Seabrook Station Technical Specification Figure 5.1-1.

i e

B.1-26 ODCM Rev. 16 l

TABLE B.1-14 DOSE AND DOSE RAM FACTORS SPECIFIC FOR THE SCIENCE & NATURE CENTER FOR IODINE. TRITIUM. AND PARTICUIATE RELEASES A

Critical organ Critical Organ Dose Factor for Critical Organ Dose Critical Organ Dose Dose Factor for Cround Level Rate Factor for Rate Factor for Elevated Relekse Elevated Release Ground Level Release Release Point Point Point Point Ra pra,,,,, ( mey 3 pyg,,,, ( cYI D#"***

I p5 ' I D " ***'O I p$ I H-3 6.45E.11 9.27E-10 2.03E-03 2.92E-02 Cr-51 4.98E-09 2.88E-08 2.12E-01 1.11E+00 Mn-54 1.39E-06 5.71E-06 6.24E+01 2.39E+02 Fe-59 3.09E-07 1.89E-06 1.29E+01 7.16E+01 Co-58 3.89E-07 2.10E-06 1.72E+01 8.26E+01 Co-60 2.17E-05 8.03E-05 9.87E+02 3.63E+03 Zn-65 7.34E-07 3.19E-06 3.31E+01 1.33E+02 Sr-89 1.15E-07 1.61E-06 3.63E+00 5.08E+01 Sr-90 5.14E-06 7.19E-05 1.62E+02 2.27E+03 Zr-95 3.38E-07 2.57E-06 1.35E+01 9.15E+01 Nb-95 1.53E-07 9.35E-07 6.43E+00 3.53E+01

[~')N

\._,

Mo-99 1.62E-08 1.92E-07 5.58E-01 6.21E+00 1

j l

Ru-103 1.30E-07 8.64E-07 5.33E+00 3.19E+01 Ag-110m 3.43E-06 1.54E-05 1.55E+02 6.34E+02 Sb-124 6.96E-07 4.46E-06 2.89E+01 1.67E+02 1-131 7.79E-07 1.08E-05 2.47E+01 3.41E+02 I-133 1.84E-07 2.56E-06 5.83E+00 8.11E+01 Cs-134 6.83E-06 2.53E-05 3.08E+02 1.14E+03 Cs-137 1.03E-05 3.81E-05 4.64E+02 1.72E+03 Ba.140 1.14E-07 1.42E-06 3.85E+00 4.54E+01 Ce-141 4.09E-08 4.51E-07 1.45E+00 1.48E+01 Ce-144 6.95E-07 9.11E-06 2.27E+01 2.90E+02 Othe r* 2.26E-06 9.24E-06 1.02E+02 3.91E+02

Dose factors to be used in Method I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.

B.1-27 ODCM Rev. 16

l TABLE B.1-15 i l

DOSE AND DOSE RATE FACTORS SPECIFIC FOR THE " ROCKS" FOR IODINE. TRITIUM. AND PARTICUIATE RELEAjXS, Critical Organ Critical Organ Critical Organ Dose Critical Organ Dose O

Dose Factor Dase Factor for Rate Factor for Rate Factor for for Elevated Ground Level Elevated Release Ground Level Release Point Release Point Point Release Point Radio- omw ,,gmrem) og ,, g mr ""~"'*3 ( pci-yr ) Dm's ,3 ( "pei-yr9 )

pei pc nuclide H-3 6.85E-10 6.45E-09 2.16E-02 2.03E-01 Cr-51 2.68E-08 1.75E-07 1.07E+00 6.53E+00 Mn-54 5.84E-06 3.18E-05 2.55E+02 1.31E+03 Fe-59 1.74E-06 1.17E-05 6.78E+01 4.29E+02 Co-58 2.01E-06 1.25E-05 8.11E+01 4.79E+02 Co-60 8.83E-05 4.09E-04 3.97E+03 1.85E+04 Zn-65 3.23E-06 1.80E-05 1.37E+02 7.29E+02 Sr-89 1.23E-06 1.15E-05 3.88E+01 3.63E+02 Sr-90 5.48E-05 5.14E-04 1.73E+03 1.62E+04 Zr-95 2.22E-06 1.68E-05 8.14E+01 5.83E+02 Nb-95 8.59E-07 5.79E-06 3.37E+01 2.13E+02 Mo-99 1.50E-07 1.34E-06 4.92E+00 4.32E+01 Ru-103 7.74E-07 5.47E-06 2.95E+01 1.96E+02 Ag-110m 1.54E-05 8.77E-05 6.47E+02 3.53E+03 Sb-124 4.04E-06 2.80E-05 1.56E+02 1.01E+03 l

I-131 8.27E-06 7.73E-05 2.61E+02 2.44E+03 :

l f

I-133 1.95E-06 1.83E-05 6.18E+01 5.77E+02 Cs-134 2.78E-05 1.29E-04 1.25E+03 5.80E+03 Cs-137 4.19E-05 1.94E-04 1.89E+03 8.77E+03 Ba-140 1.10E-06 9.99E-06 3.56E+01 3.19E+02 l Ce-141 3.59E-07 3.14E-06 1.20E+01 1.02E+02 l Ce-144 7.02E-06 6.46E-05 2.25E+02 2.05E+03 Other* 9.56E-06 5.09E-05 4.16E+02 2.12E+03 ,

O Dose factors to be used in Method I calculations for any "other" detected gamma !

I emitting radionuclide which is not included in the above list.

O\

B.1-28 ODCM Rev. 16 l

J

2.0 METHOD TO CALCUIATE OFF-SITE LIOUID CONCENTRATIONS Chapter 2 contains the basis for station procedures used to demonstrate compliance with Technical Specification 3.11.1.1, which limits the total fraction of O MFC in liquid pathways, other than noble gases (denoted here ast F ") at the point of discharge from the station to the environment (see Figure B.6-1). Ft " is limited to less than or equal to one, i.e.,

Ff $ 1.

The total concentration of all dissolved and entrained noble gases at the point of discharge from the multiport diffuser from all station sources combined, denoted C t

", is limited to 2E-04 pCi/ml, i.e.,

Ct " f 2E-04 pCi/ml.

Appendix C, Attachments 3 and 4, provide the option and bases for the use of the EMS determination of liquid concentration limits for plant discharges to the environment.

2.1 METHOD TO DETERMINE t F " AND C3 "

First, determine the total fraction of MFC (excluding noble gases), at the point of discharge from the station from all significant liquid sources denoted Ft " ; and then separately determine the total concentration at the point of discharge of all dissolved and entrained noble gases from all station sources, denoted Ct ", as follows:

h ENG E

b E MPC $ 1. (2-1)

V F1 -

p i i (NpCi/ml) and:

NG NG C - E qi $ 2E-04 (2-2) 1 i

(pCi/ml) (pCi/ml) (pCi/ml) where:

- Total fraction of MPC in liquids, excluding noble Ff0 gases, at the point of discharge from the multiport diffuser. 1 i

O B.2-1 ODCM Rev. 16

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2.1 METHOD TO DETERMINE t F " ANDt C " (Continued) l Cpt - Concentration at point of discharge from the multiport diffuser of radionuclide "i", except for dissolved and entrained noblo i I

gases, from all tanks and other significant sources, p, from which a discharge may be made (including the waste test tanks and any other significant source from which a discharge can be made) .

C,1 is determined by dividing the product of the measured radionuclide concentration in liquid waste test tanks, PCCW, steam generat.or blowdown, or other effluent streams times their !

discharge flow rate by the total available dilution water flow rate of circulating and service water at the time of release (pCi/ml). f i

MPC i - Maximum permissible concentration of radionuclide "i" except for l dissolved and entrained noble gases from 10CFR20, Appendix B, Table II, Column 2 (pCi/ml). See Appendix B for a list of MPC values.

C" 2

- Total concentration at point of discharge of all dissolved and entrained noble gases in liquids from all station sources (pci/ml)

Cu" - Concentration at point of discharge of dissolved and entrained noble gas "i" in liquids from all station sources (pCi/ml) 2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE 2.2.1 Waste Test Tanks Cpt is determined for each radionuclide detected from the activity in a representative grab sample of any of the waste test tanks and the predicted flow at the point of discharge.

The batch releases are normally made from two 25,000-gallon capacity waste test tanks. These tanks normally hold liquid waste evaporator distillate. The waste test tanks can also contain other waste such as liquid taken directly from the floor drain tanks when that liquid does not require processing in the evaporator, distillate from the boron recovery evaporator when the BRS evaporator is cubstituting for the waste evaporator, and distillate from the Steam Generator Blowdown System evaporators and flash steam condensers when that system must discharge liquid off-site.

If testing indicates that purification of the waste test tank contents is required prior to release, the liquid can be circulated through the waste damineralizer and filter.

The contents of the waste test tank may be reused in the Nuclear System if the sample test meets the purity requirements.

Prior to discharge, each waste test tank is analyzed for principal gamma emitters in accordance with the liquid sample and analysis program outlined in Part A to the ODCM.

O B.2-2 ODCM Rev. 16

2.2 METHOD TO DETERMINE FADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE 2.2.2 Turbine Buildine Sumo N

l The Turbine Building sump collects leakage from the Turbine Building floor drains and discharges the liquid unprocessed to the circulating water system.

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Szepling of this potential source is normally done once per week for l

determining the radioactivity released to the environment (see Table A.3-1).

2.2.3 Steam Cenerator Blowdown Flash Tank The steam generator blowdown evaporators normally process the liquid from the l

steam generator blowdown flash tank when there is primary to secondary leakage.

I Distillate from the evaporators can be sent to the waste test tanks or recycled to the condensate system. When there is no primary to secondary leakage, flash tank i liquid is processed through the steam generator blowdown demineralizers and returned to the secondary side, l Steam generator blowdown is only subject to sampling and analysis when all or part of the blowdown liquid is being discharged to the environment instead of the normal recycling process (see Table A.3-1).

2.2.4 Primary Comoonent Cooline Water (PCCW) System The PCCW System is used to cool selected primary components.

l The system is normally sampled weekly to determine if there is any radwaste j in-leakage. If leakage has been determined, the Service Water System is sampled to

! determine if any release to the environment has occurred.

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B.2-3 ODCM Rev. 16

3.0 OFF-SITE DOSE CAlfUIATION METHODS Chapter 3 provides the basis for station procedures required to meet the Radiological Effluent Technical Specifications (RETS) dose and dose rate O requirements contained in Section 3/4.11 of the station operating Technical Specifications. A simple, conservative method .(called Method I) is listed in Tables B.1-2 to B.1-7 for each of the requirements of the RETS. Each of the Method I equations is presented in Sections 3.2 through 3.9. As an alternate to Method I, ,

the EMS computer program documented in Appendix C can be used to determine j regulatory compliance for effluent dos,es and dose rates. The use of the EMS software is designated as Method IA in Chapter 3. In addition, those sections include more sophisticated methods (called Method II) for use when more refined results are needed. This chapter provides the methods, data, and reference material with which the operator can calculate the needed doses, dose rates and setpoints.

For the rquirements to demonstrate compliance with Technical Specification off-site dose limits, the contribution from all measured ground level releases must be added to the calculated contribution from the vent stack to determine the Station's total radiological impact. The bases for the dose and dose rate equations are given in Chapter 7.0. Method IA bases and software verification documentation are contained in Appendix C.

The Annual Radioactive Effluent Release Report, to be filed after January 1 each year per Technical Specification 6.8.1.4, requires that meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, be used for determining the gaseous pathway doses. For continuous release sources (i.e. , plant vent, condenser air removal exhaust, and gland steam packing exhauster), concurrent quarterly average meteorology will be used in the dose calculations along with the quarterly total radioactivity released. For batch releases or identifiable operational activities (i.e. , containment purge or venting to atmosphere of the O Waste Gas System), concurrent meteorology during the period of release will be used to determine dose if the total noble gas or iodine and particulates released in the batch exceeds five percent of the total quarterly radioactivity released from the unit; otherwise quarterly average noteorology will be applied. Quarterly average meteorology will also be applied to batch releases if the hourly met data for the period of batch release is unavailable.

l Annual dose assessment reports prepared in accordance with the requirements of the ODCM will include a statement indicating that the appropriate portions of Regulatory Guide 1.109 (as identified in the individual subsections of the ODCM for each class of effluent exposure) have been used to determine dose impact from station releases. Any deviation from the methodology, assumptions, or parameters given in Regulatory Guide 1.109, and not already identified in the bases of the ODCM, will be explicitly described in the effluent report, along with the bases for the deviation.

O B.3-1 ODCM Rev. 16

3.1 INTRODUCTORY CONCEPTS In part, the Radiological Effluent Technical Specifications (RETS) limit dose er dose rate. The term " dose" for ingested or inhaled radioactivity means the dose crmmitment, measured in mrem, which results from the exposure to radioactive materials that, because of uptake and deposition in the body, will continue to cxpose the body to radiation for some period of time after the source of rcdioactivity is stopped. The time frame over which the dose commitment is svaluated is 50 years. The phrases " annual dose" or " dose in one year" then refers to the 50-year dose commitment resulting from exposure to one year's worth of raleases. " Dose in a quarter" similarly means the 50-year dose commitment resulting from exposure to one quarter's releases. The term " dose," with respect to external exposures, such as to noble gas clouds, refers only to the doces received during the cetual time period of exposure to the radioactivity released from the plant. Once the source of the radioactivity is removed, there is no longer any additional eceumulation to the dose commitment.

" Dose rate" is the total dose or dose commitment divided by exposure period.

For example, an individual who is exposed via the ingestion of milk for one year to rtdioactivity from plant gaseous effluents and receives a 50-year dose commitment of 10 mrem is said to have been exposed to a dose rate of 10 mrem / year, even though the cetual dose received in the year of exposure may be less than 10 mrem.

In addition to limits on dose commitment, gaseous effluents from the station cre also controlled so that the maximum or peak dose rates at the site boundary at cny time are limited to the equivalent annual dose limits of 10CFR, Part 20 to unrestricted areas (if it were assumed that the peak dose rates continued for one y2ar). These dose rate limits provide reasonabla assurance that members of the public, either inside or outside the site boundary, will not be exposed to annual cveraged concentrations exe , ding the limits specified in Appendix B, Table II of 10CFR, Part 20 (10CFR20.106(a)) . See Appendix B for a listing of these concentration limits.

The quantities AD and b are introduced to provide calculable quantities, related to off-site doses or dose rates that demonstrate compliance with the RETS.

Delta D, denoted AD, is the quantity calculated by the Chapter 3, Method I dose equations. It represents the conservative increment in dose. The AD calculated by Method I equations is not necessarily the actual dose received by a real individual, but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the selection and definition of critical receptors. The radionuclide specific dose factors in each Method I dose squation represent the greatest dose to any organ of any age group. (Organ dose is a function of age because organ mass and intake are functions of age.) The critical receptor assumed by " Method I" equations is then generally a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is higher l than any real individual is likely to receive. Method IA dose calculations using I the EMS sof tware evaluate each age group and organ combination to determine the !

maximum organ dose for each mix of radionuclides specified in a release period. l Method II also allows for a more exact dose calculstion for each individual if necessary.

O1l B.3-2 ODCM Rev. 16

3.1 INTRODUCTORY CONCEPTS (Ccntinusd)

D dot, denoted 6, is the quantity calculated in the Chapter 3 dose ras.g equations. It is calculated using the station's effluent monitoring system reading and an annual or long-term average atmospheric dispersion factor, b predicts the maximum off-site annual dose if the peak observed radioactivity release rate from the plant stack continued for one entire year. Since peak release rates, or resulting dose rates, are usually of short time duration on the order of an hour or less, this approach then provides assurance that 10CFR20.106 limits will be met.

Each of the methods to calculate dose or dose rate are presented in the following subsections. Each dose type has two levels of complexity. Method I is the simplest and contains many conservative factors. As an alternate to Method I the EMS computer program documented in Appendix C can be used to determine regulatory compliance for effluent doses and dose rates. The use of the EMS system is designated as Method IA in Chapter 3.

Method II is a more realistic analysis which makes use of the models in Regulatory Guide 1.109 (Revision 1), as noted in each subsection of Chapter 3 for the various exposure types. A detailed description of the methodology, assumptions, and input parameters to the dose models that are applied in each Method II calculation, if not already explicitly described in the ODCM, shall be documented and provided when this option is used for NRC reporting and Technical Specification dose compliance.

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B.3-3 ODCM Rev. 16

3.2 METHOD TO CALCUIATE THE TOTAL BODY DOSE FROM LIQUID RELEASES Technical Specification 3.11.1.2 limits che total body dose commitment to a member of the publ*c from radioactive material in liquid effluents to 1.5 mrem per quarter and 3 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when the total body dose estimate exceeds 0.06 mrem in any 31-day period. Technical Specification 3.11.4 limits the total body dose commitment to any real member of the public from all station sources (including liquids) to j 25 mrem in a year.

l Use Method I or Method IA first to calculate the maximum tctal body dore from l

a liquid release from the station as it is simpler to execute and more conservative than Method II.

Use Method II if a more refined calculation of total body dose is needed, l 1.e. , Method I or Method IA indicates the dose might be greater than the Technical Specification limits.

To evaluate the total body dose, use Equation 3.1 to estimate the dose from the planned release and add this to the total body dose accumulated from prior releases during the month. See Section 7.1.1 for basis.

3.2.1 Method I The increment in total body dose from a liquid release is:

1 Du , = k { Q tDFLiui i

(3-1)

(mrem) = ( ) (pci) where DFLi u, - Site-specific total body dose factor (arem/pci) for a liquid release. It is the highest of the four age groups. See Table B.1-11.

Qi - Total activity (pCi) released for radionuclide "i". (For stroatiums, use the most recent measurement available.)

K- 918/F4 ; where Fa is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3/sec). For normal )

3 operations with a cooling water flow of 918 f t /sec, K is equal to 1.

Equation 3-1 can be applied under the following condir. ions (otherwise, justify Method I or consider Method II):

1. Liquid releares via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and

2. Any continuous or batch release over any time period.

O B.3-4 ODCM Rev. 16

f 3.2 METHOD TO CALCULATE THE TOTAL BODY DOSE FROM LIQUID RELEASES 3.2.1 Method I (Continued) m Method IA is implemented by the EMS software as described in Appendix C.

Liquid release models are detailed in sections 2.1 - 2.6 of ths EMS Technical Reference Manual (Attachment 4 of Appendix C).

3.2.2 Method II Method II consists of the models, input data and assumptions (bicaccumulation

! factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific l data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, are also applied to {

1 Method II assessments, except that doses calculated to the whole body from j radioactive effluents are evaluated for each of the four age groups to determine the maximum whole body dose of an age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors of Method II calculations. As noted l in Section B.7.1, the mixir s ratio associated with the edge of the l'F surface i isotherm above the multiport diffuser may be used in Method II calculations for the shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit taken for mixing zone dilution to the same value assumed in Method I (M, - 0.10) .

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B.3-5 ODCM Rev. 16 l

3.3 METHOD TO CALCUIATE MAXIMUM ORCAN DOSE FROM LIQUID RELEASES Technical Specification 3.11.1.2 limits the maximum organ dose commitment to a M:aber of the Public from radioactive material in liquid effluents to 5 mrem per quarter and 10 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radvaste treatment when the maximum organ dose projected exceeds 0.2 mrem in cny 31 days (see Subsection 3.11 for dose projections) . Technical Specification 3.11.4 limits the maximum organ dose commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year.

l Use Methed I or Method IA first to calculate the maximum organ dose from a liquid release to unrestricted areas (see Figure B.6-1) as it is simpler to execute end more conservative than Method II.

Use Method II if a more refined calculation of organ dose is needed, l 1.e. , Method I or Method IA indicates the dose may be greater than the limit.

Use Equation 3-2 to estimate the maximum organ dose from individual or ccabined liquid releases. See Section 7.1.2 for basis.

3.3.1 Method I The increment in maximum organ dose from a liquid release is:

D=k Qi DFLw (3-2)

(mrem) = ( ) (pC1) where DFLw - Site-specific maximum organ dose factor (mrem /pC1) for a liquid release. It is the highest of the four age groups. See Table B.1-ll.

Q4 - Total activity (pCi) released for radionuclide "i". (For :

strontiums, use the most recent measurement available.) f K- 918/F4 ; where F4 is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3 /sec). For normal operations with a cooling water flow of 918 ft3 /sec, K is equal to 1.

Equation 3-2 can be applied under the following conditions (otherwise, justify Method I or consider Method II): j

1. Liquid relerses via the multiport diffuser to unrestricted areas (at the ;

edge of the initial mixing or , rompt dilution zone that corresponds to a ,

factor of 10 dilution), and j

2. Any continuous or batch release over any time period.

O' B.3-6 ODCM Rev. 16

3.3 METHOD TO CALCUIATE MAXIMUM ORGAN DOSE FROM LIQUID RELEASES 3.3.1 Method I (Continued)

( Method IA is implemented by the EMS software as described in Appendix C.

Liquid release models are detailed in sections 2.1 - 2.6 of the EMS Technical Reference Manual (Attachment 4 of Appendix C).

3.3.2 Method II Method II consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup times) in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, are also applied to Method II assessments, except that doses calculated to critical organs from radioactive effluents are evaluated for each of the four age groups to determine the maximum critical organ of an age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors for Method II calculations. As noted in Section B.7.1, the mixing ratio associated with the edge of the l'F surface isotherm above the multiport diffuser may be used in Method II calculations for the shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit taken for mixing zone dilution to the same value assumed in Method I (M, - 0.10) .

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O B.3-7 ODCM Rev. 16

3.4 KETHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBl E GASES Technical Specification 3.11.2.1 limits the dose rate at any time to the total b dy from noble gases at any location at or beyond the site boundary to 500 mrem / year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate.

By limiting D a to a rate equivalent to no more than 500 mrem / year, we assure that the total body dose accrued in any one year by any member of the general public is loss than 500 mrem.

l Use Method I or Method IA first to calculate the Total Body Dose Rate from the paak release rate via the station vents or ground level effluent release points.

M2thod I applies at all release rates.

Use Method II if a more refined calculation of ba is desired by the station (i.e., use of actual release point parameters with annual or actual meteorology to I l cbtain release-specific X/Qs) or if Method I or Method IA predicts a dose rate greater than the Technical Specification limit to determine if it had actually been sxceeded during a short time interval. See Section 7.2.1 for basis.

Compliance with the dose rate limits for noble gases are continuously d:monstrated when effluent release rates are below the plant vent noble gas activity tonitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit, or a value below it. l D3 terminations of dose rate for compliance with Technical Specifications are i

performed when the effluent monitor alarm setpoint is exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10, Table 3.3-10) when the renitor is inoperable.

3.4.1 Method I The Total Body Dose Rate to an off-site receptor due to noble gases in 9 l' effluents released via the plant vent can be determined as follows:

0.85

DFB3 )

bam = * {1 ("Q i (3-3a) arem ,'pCi-sec' 'pCi 8

' mrem-m' p ,pci-yr, yr pCi-m3 , ,s e c, where ha - The off-site total body dose rate (mrem /yr) due to noble gases in elevated effluent releases.

Qi - the release rate at the station vents (pCi/sec), for each noble gas radionuclide, "i", shown in Table B.1-10, and DFB t - total body gamma dose factor (see Table B.1-10).

The Total Body Dose Rate (to an off-site receptor) due to noble gas in ground level effluent releases can be determined as follows:

O B.3-8 ODCM Rev. 16

3.4 METHOD TO CALCULATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES I 3.4.1 Method I (Continued) bs3g,3 = 3.4 * {i ("Qi

DFB ) i (3-3b) arem ,'pCi-sec' 'gCi 'arem-m8 '

yr 3

,p ,

CL-m , ,s e c, ,pci-yr, where l

bu, - The total off-site body dose rate (arem/yr) due to noble gases in elevated effluent releases, and Qi and DFBi are as defined for Equation 3-3a.

For the special on-site receptor locations, the Science & Nature Center and the " Rocks," the total body dose rates due to noble gases in effluent discharges can l be determined as folices: 1 1

For the Science & Nature Center, elevated effluent release:

l bs3rc,3 - 0.0015 * { (Qi

DFB3 ) (3-3c) I i

For the Science & Nature Center, ground level effluent release:

( Dt3gg,3 - 0.0074 * { (Q i* DFBi ) (3-3d)

( i For the " Rocks," elevated effluent release:

6tba(.) = 0.038 * { (Qi

DFBi ) (3-3e) i For the " Rocks," ground level effluent release: ,

l Dtbn(s) - 0.2 * {i(Qi

DFB ) i (3-3f) where Dtbr(.). DtbE(s)s b tbR(.), and h tht - The total body dose rate (arem/yr) l at the Science & Nature Center and the " Rocks," respectively, due to noble gases in gaseous discharges from elevated (e) and ground level (g) re".aase points, and Qi and DFB are as defined previously.

3 Equations 3-3a through 3-3f can be applied under the following conditions

[ (otherwise, justify Method I or consider Method II):

(

B.3-9 ODCM Rev. 16

3.4 METHOD TO CAlEULATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES 3.4.1 Method I (Continued)

1. Normal operations (nonemergency event), and

2. Noble gas releases via any station vent to the atmosphere.

Method IA is implemented by the EMS softwere as described in Appendix C.

G:seous release models are detailed in Section 6.7.3 of the EMS Software {

Requirements Specification (Attachment 3 of Appendix C).

3.4.2 Method II Method II consists of the model and input data (whole body dose factors) in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or casumptions have been identified in the ODCM. The general equation (B-8) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I cpproach as described in the Bases section, is also applied to a Method II cesessment. No credit for a shielding factor (SF ) associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor identified in ODCM Equation 7-3 (Section 7.2.1), and determined as indicated in Section 7.3.2 for the release point (oither ground level or vent stack) from which recorded effluents have been discharged.

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B.3-10 ODCM Rev. 16

3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES Technical Specification 3.11.2.1 limits the dose rate at any time to the skin from noble gases at any location at or beyond the site boundary to O 3,000 mrom/ year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate.

By limiting baa to a rate equivalent to no more than 3,000 mres/ year, we assure that the skin dose accrued in any one yesr by any reember of the general public is less than 3,000 mrom. Since it can be expected tl.at the peak release rate on which bga is derived would not be exceeded without corrective action being taken to lower it, the resultant average release rate over the year is expected to be considerably less than the peak release rate.

l Use Method I or Method IA first to calculate the Skin Dose Rate from peak release rate via station vents. Method I applies at all release races.

Use Method II if a more refined calculation of b.ga is desired by the station i.e. , use of actual release point parameters with annual or actual meteorology to l o(btain release-specific X/Qs) or if Method I or Method IA predicts a dose rate ;

greater than the Technical Specification limit to determine if it had actually been '

exceeded during a short time interval. See Section 7.2.2 for basis.

Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit, or a value below it.

Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded.

J 3.5.1 Method 1 For an off-site receptor and elevated effluent release, the Skin Dose Rate due to noble gases is:

Dak at.) [ (Qi DF'ic.3)

(3-4a) arem ,,p 's ic' 'arem-sec' y: ,s e c, ,

pCi-yr ,

where 6,ging,3 - the off-site skin dose rate (ares /yr) due to noble gases in an effluent discharge from an elevated release point, Qi

- as defined previously, and D6g,3 - the combined skin dose factor for elevated discharges (see Table B.1-10).

B.3-11 ODCM Rev, 16

3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES 3.5.1 Method I (Continued)

For an off-site receptor and ground level release, the skin dose rate due to noble gases is:

Daug,3- (Qi eDIc,3) t (3-4b) where beag,3 - The off-site skin dose rate (mrem /yr) due to noble gases in an effluent discharge from a ground level release point, Qi - as defined previously, and DI ic,3 - The combined skin dose factor for ground tevel discharges (see Table B.1-10) .

l For an on-site receptor at the Science & Nature Center and e!= rated release conditions, the skin dose rate due to noble gases is:

Daart.) - 0.0014 * (Qi* dig i<,3) (3-4c) where D a arc.3

- The skin dose rate (mrem /yr) at the Science & Nature Center due to noble gases in an elevated release, j Qi

- as defined previously, and DIzte) i

- the combined skin dose factor for elevated discharges (see Table B.1-13).

For an on-site receptor at the Science & Nature Cents.r and ground level {

release conditions, the skin dose rate due to noble gases is: !

beingc ) - 0.0014 * (Qi*DIzc,3) t (3-4d) where i

Baarts) - the skin dose rate (arem/yr) at the Science & Nature Center due i to noble gases in a ground level release, Q, - as i ?ined previously, and DIrc,3 i

. rhe combined skin dose factor for ground level discharges (see Table B.1-13).

O B.3-12 ODCM Rev. 16

3.5 METHOD TO CALCULATE THE SKIN DOSE RATE FROM NOBLE GASES 3.5.1 Method I (Continued) bi For an on-site receptor at the " Rocks" and elevated release conditions, the U skin dose rate due to noble gases is:

baigc,3 - 0.0076 * (Qi

Ding,3) i (3-4e) where baigc 3 - the skin dose rate at the " Rocks" due to noble gases in an elevated release, Qi - as defined previously, and DI is(*) - The combined skin dose factor for elevated. discharges (see Table B.1-13).

For an on-site receptor at the " Rocks" and ground level release conditions, the skin dose rate due to noble gases is:

baig

- 0.0076 * (Qi*DIa(s)) t (3-4f) where baigg,3 the skin dose rate (arem/yr) at the " Rocks" due to noble gases in O a ground level release, Qi - as defined previously, and DIa(s) t - the combined skin dose factor for ground level discharges (see Table B.1-13). Equations 3-4a through 3 4f can be applied under the following conditions (otherwise, justify Method I or consider Method II).

1. Normal operations (nonemergency event), and

2. Noble gas releases via any station vent to the atmosphere.

Method IA is implemented by the EMS sof tware as described in Appendix C. Caseous release models are detailed in Section 6.7.3 of the EMS Software Raquirements Specification (Attachment 3 of Appendix C) . O B.3-13 ODCM Rev. 16 ] l 3.5 METHOD TO CALCU1 ATE THE SKIN DOSE RATE FROM NOBLE CASES 3.5.2 Method II Method II consists of the model and input data (skin dose factors) in Rsgulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or cecumptions have been identified in the ODCM. The general equation (B-9) taken from Ragulatory Guide 1.109, and used in the derivation of the simplified Method I cpproach as described in the Bases section, is also applied to a Method 11 cr essment, no credit for a shieldin5 factor (SF) associated with residential ctructurer is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor and undepleted atmospheric dicpersion factor identified in ODCM Equation 7-8 (Section 7.2.2), and determined as indicted in Sections 7.3.2 and 7.3.3 for the release point (either ground level or v:nt stack) from which recorded effluents have been discharged. O l l f ( O B.3-14 ODCM Rev. 16 I I l 3.6 METHOD TO CAI4ULATE THE CRITICAL ORGAN DOSE RATE FROM 10 DINES, TRITIUM AND PARTICUIATES WITH Tt/2 GREATER THAN 8 DAYS O Technical Specification 3.11.2.1 limits the dose rate at any time to any organ .() from 1:11, tasy, sH and radionuclides in particulate form with half lives greater than 8 days to 1500 mres/ year to any organ. The Technical Specification indirectly limits peak release rates by limiting the dose-rate that is predicted from continued release at the peak rate. By limiting b , to a rate equivalent to no more than 1500 arem/ year, we assure that the critical organ dose accrued in any one year by any member of the general public is less than 1500 mram. l Use Method I or Method IA first to calculate the Critical Organ Dose Rate from the peak release rate via the station vents. Method I applies at all release rates. Use Method II if a more refined calculation of b,, is desired by the station (i.e. , use of actual release point parameters with annual or actual meteorology to l obtain release-specific X/Qs) or if Method I or Method IA predicts a dose rate greater than the Technical Specification limit to determine if it had actually been exceeded during a short time interval. See Section 7.2.3 for basis. 3.6.1 Method I i The Critical Organ Dose Rate to an off-site receptor and elevated release I conditions can be determined as follows: 1 1 (3-Sa) D..( ) = (Q

DFGge,(,))

( mrem) _ { ( pCi) see , ( mrem-sec) pCi-yr yr ( I where b,,c,3 - The off-site critical organ dose rate (arem/yr) due to iodine, tritium, and particulates in an elevated release, Qi - the activity release rate at the station vents of radionuclide "i" in pCi/see (i.e. , total activity measured of radionuclide "i" averaged over the time period for which the filter / charcoal l sample collector was in the effluent stream. For i - Sr89 or Sr90, use the best estimates, such as most recent measurements), and DFG' s,.g,3 - the site-specific critical organ dose rate factor ( mram-sec) for an elevated gaseous release (see Table B.1-12) . pci-yr B.3-15 ODCM Rev. 16 3.6 KETHOD TO CALCULATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM AND PARTICUIATES WITH Tua GREATER THAN 8 DAYS 1 3.6.1 Method I (Continued) For an off-site receptor and ground level release, the critical organ dose l rete can be determined as follows: Deo(s) - [(41 DFG't. g,3) (3-Sb) whsre b,,g,3 - the off-site critical organ dose rate (mrem /yr) due to iodine, tritium, and particulates in a ground level release, Qi - as defined previously, and DFG[ cog,3 - the site-specific critical organ dose rate factor for a ground . level gaseous discharge (see Table B.1-12). ! For an on-site receptor at the Science & Nature Center and elevated release conditions, the critical organ dose rate can be determined as follows: D ee r<.)- 0.0014 * { (Qi DFG[,,gg,3) (3-Sc) i where b,,gg,3 - The critical organ dose rate (mrem /yr) to a receptor at the Science & Nature Center due to iodine, tritium, and particulates in an elevated release, Qi - as defined previously, and DFG[,,gg,3 - the Science & Nature Center-specific critical organ dose rate factor for an elevated discharge (see Table B.1-14). O B.3-16 ODCM Rev. 16 3.6 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM AND PARTICUIATES WITH Tuz GREATER THAN 8 DAYS 3.6.1 Method I (Continued) For an on-site receptor at the Science & Nature Center and ground level release conditions, the critical organ dose rate is: 6,gg,3 - 0.0014 * [(Qi

DFG[ gg,3) (3-5d) where b gg,3 - the critical organ dose rate (ares /yr) to a receptor at the Science & Nature Center due to iodine, tritium, and particulates l in a ground level release, Qi - as defined previously, and DFG1,gg,3- the Science & Nature Center-specific critical organ dose rate factor for a ground level discharge (see Table B.1-14) .

For an on-site receptor at the " Rocks" and elevated release conditions, the l critical organ dose rate is: 6,gg,3 - 0.0076

E (Qi

DFU[,gg,3) (3-Se) l where 6,gg,3 - The critical organ dose rate (arem/yr) to a receptor at the

" Rocks" due to iodine, tritium, and particulates in an elevated release, l Qi - as defined previously, and DFG$,gg,3 - the " Rocks"-specific critical organ dose rate factor for an elevated discharge (see Table B.1-15). For an on-site receptor at the " Rocks' and ground level release conditions, the critical organ dose rate is: 6,gg,3 - 0.0076 * { (Qi

DFGl gg,3) (3-Sf) i where b, ,and Qi - are as defined previously, and DFG$,gg,3 - the " Rocks"-specific critical organ dose rate factor for a ground level discharge (see Table B.1-15).

B.3-17 ODCM Rev. 16 I 3.6 METHOD TO CAI4ULATE THE CRITICAL ORGAN DOSE RATE FROM 10 DINES, TRITIUM AND PARTICUIATES WITH Tu2 GREATER THAN 8 DAYS I 3.6.1 Method I (Continued) ! Equations 3-Sa through 3-5f can be applied under the following conditions l (otherwise, justify Method I or consider Method II):

1. Normal operations (not emergency event), and

2. Tritium, I-131 and particulate releases via monitored station vents to the atmosphere.

Method IA is implemented by the EMS sof tware as described in Appendix C. Cn eous release models are detailed in Section 6.7.3 of the EMS Software Rzquirements Specification (Attachment 3 of Appendix C). 3.6.2 Method II Method II consists of the models, input data and assumptions in Appendix C of Rsgulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or cecumptions have been identified in the ODCM (see Tables B.7-2 and B.7-3) . The critical organ dose rate will be determined based on the location (site boundary, naerest resident, or farm) of receptor pathways as identified in the most recent cnnual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy veget. ables, milk, and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground icvel or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age groups independently, cnd take no credit for a shielding factor (Sr) associated with residential structures. l 1 O B.3-18 ODCM Rev. 16 l 3.7 METHOD TO CALCULATE THE CAMMA AIR DOSE FROM NOBLE GASES Technical Specification 3.11.2.2 limits the gamma dose to air from noble gases at any location at or beyond the site boundary to 5 mrad in any quarter and 10 mrad O in any year per unit. Dose evaluation is required at least once per 31 days. l Use Method I or Method IA first to calculate the gamma air dose from the station gaseous ef fluent releases during the period. Use Method II if a more refined calculation is needed (i.e. , use of actual release point parameter with annual or actual meteorology to obtain release-specific l X/Qs), or if Method I or Method IA predicts a dose greater than the Technical Specification limit to determine if it had actually been exceeded. See Section 7.2.4 for basis. l 3.7.1 Method I The general form of the gamma air dose equation is: (3-6) D'i, = 3.17E-02 * [X/Q]Sm

t-* * [ (Qi

DFl)

PCi-yr sec mrad-m8 )*{(pci) (mrad) = ,7,* ( u pCi-sec, .pCi-yr. where Di g, is the gamma air dose. 3.17E-02 is the number of pCi per pCi divided by the number of second { per year, [X/Q]'a, is the 1-hour gamma atmospheric dispersion factor, t-* is a unitiess factor which adjusts the 1-hour [X/Q]1 value for a release with a total duration of t hours, Qi is the total activity in pCi of each radionuclide "i" released to the atmosphere from the station gaseous effluent release point during the period of interest, and DF1 1 is the gamma dose factor to air for radionuclide "i" (see Table B.1-10). Incorporating receptor location-specific atmospheric dispersion factors ([X/Q]1), adjustment factors (t-*) for elevated and ground-level effluent release conditions, and occupancy factors when applicable (see Section 7.2.7), yields a series of equations by which the gamma air dose can be determined.

a. Maximum off site receptor location, elevated release conditions:

(3-6a) D 11 ,c,3 = 3.2E-07

t-o.m , (qs , pp7) r ,

mrad-m8 ) (arad) = PC i-yr *( )*{(pCi) U ,pci-m3, ,PCi yr , B.3-19 ODCM Rev. 16 l 3.7 METHOD TO CALCUIATE THE GAMMA AIR DOSE FROM NOBLE GASES 3.7.1 Method I (Continued)

b. Maximum off-site receptor location, ground-level release conditions:

(3-6b) D]1,c,3= 1.6E-06

t-o.2os . (qt . 9 77) 1 Ci-yr' * ( " rad-m f f (mrad) = Py )* (pCi) -

,P W l , Ci-m3, ,

c. Science & Nature Center receptor elevated release conditions:

Dji,gg,3 = 4.9E-10

t-o.252 * { (Q3

DFI) (3-6c) 8 Ci-yr (mrad) = ( PpCi-m 3 ) * (

) { (pci

mad-m PCI-yr

)

d. Science & Nature Center receptor; ground-level release conditions:

D]i,gg,3 = 4.4E-09

t-o.321 * { (Qi

DFZ) (3-6d) 3 (mrad) = ( PCi-yr)3

( ) { (pCi

mrad-m PCi-yr

) pCi-m

e. Receptor at the = Rocks"; elevated release conditions:

D! trac.) = 5.lE-09

t-0155 * { (Qi

DFI) (3-6e) 3 (mrad) = ( CP i-yr) 3

( ) { (uci

mad-m PCi-yr )

pCi-m

f. Receptor at the " Rocks"; ground-level release conditions:

D11,me,) = 4.1E-08

t-o.204 * { (Qi

DFZ) (3-6f) 3 (mrad) = ( PCi-yr) *( ) (pCi

mrad-m )

pCi-m 3 PCi-yr Equations 3-6a through 3-6f can be applied under the following conditions (ctherwise justify Method I or consider Method II):

1. Normal operations (nonemergency event), and

2. Noble gas releases via station vents to the atmosphere.

l O B.3-20 ODCM Rev. 16 \ l 3.7 METHOD TO CALCUIATE TME GAMMA AIR DOSE FROM NOBLE GASES 3.7.1 Method I (Continued) Method IA is implemented by the EMS software as described in Appendix C. Gaseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.7.2 Method II

i Method II consists of the models, input data (dose factors) and assumptions in ]

l Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or assumptions have been identified in the ODCH. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified l Method I approach as described in the Bases Section 7.2.4 are also applied to Method l II assessments. Concurrent meteorology with the release period may be utilized for ! the gamma atmospheric dispersion factor identified in ODCM Equation 7-14, and determined as indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. l O , V l l l l l l /* B.3-21 ODCM Rev. 16 l { 3.8 METHOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE GASES Technical Specification 3.11.2.2 limits the beta dose to air from noble gases et any location at or beyond the site boundary to 10 mrad in any quarter and 20 mrad in any year per unit. Dose evaluation is required at least once per 31 days. l Use Method I or Method IA first to calculate the beta air dose from gaseous effluent releases during i.he period. Method I applies at all dose levels. Use Method II if a more refined calculation is needed (i.e. , use of actual rslease point parameters with annual or actual meteorology to obtain l release-specific X/Qs) or if Method I or Method IA predicts a dose greater than the T:chnical Specification limit to dstermine if it had actually been exceeded. See Saction 7.2.5 for basis. 3.8.1 tie $%i. . h m- cal form of the beta air dose equation is: D{i, = 3.17E-02 * (X/Q) w

t** * { (Qi

Dd) (3-7) f PCi-yr' 'sec' (arad) = ,

( )*{ 2Ci

mrad-m pCi-yr,

,uci-sec, f where D{i, is the beta air dose, 3.17E-02 is the number of pCi per pCi divided by the number of seconds per year, (X/Q)u is the 1-hour undepleted atmospheric dispersion factor, t** is a unitiess factor which adjusts the 1-hour X/Q value for a release with a total duration of t hours, Q3 is the total activity (pci) of each radionuclide "i" released to the atmosphere during the period of interest, and DF{ is the beta dose factor to air for radionuclide "i" (see Table B.1-10). Incorporating receptor location-specific atmospheric dispersion factor (X/Q), cdjustment factors (t**) for elevated and ground-level effluent release conditions, cnd occupancy factors when applicable (see Section 7.2.7) yields a series of squations by which the Beta Air Dose can be determined,

a. Maximum off-site receptor location, elevated release conditions:

D{1,c,3 - 4.1E-7

t*0 3 * (Qi

Dd) (3-7a) 3 (mrad) = ( pCi-yr) *( ) { (pCi

mrad-m pCi-yr

) pCi-m 3 B.3-22 ODCM Rev. 16 3.8 METHOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE GASES 3.8.1 Method I (Continued) (* ()/ b. Maximum off-site receptor location, ground level release conditions: D{i,c,3 = 6. 0E-06

t-o.ais * (Qi

Dd) (3-7b) j (arad) = ( pCi-yr) * ( ) E ( Ci * "f*d-"

3 PGi-yr ) pCi-m

c. Science & Nature Center receptor; elevated release conditions:

[ inst) = 1. 8E-09

t-o.as * (Qi

DFI) ,

(3-7c) l 3 (arad) = ( pCi-yr) *( l 3 ) { (pci e arad-m pGi yr ) pCi-3

d. Science & Nature Center receptor; ground-level release conditions:

D{ irs (s) = 2.4E-08

t-0 8'? * (Qi

Dd) (3-7d) 8 Ci-yr (mrad) = ( PpCi-m3 ) * ( ) { ( Ci , arad-m pGi-yr

)

e. Receptor at the " Rocks"; elevated release conditions:

D{1,mc.3 = 3.9E-08

t-o.24s * [ (Q

DF{} (3-7e) 3 (arad) = ( PCi-yr) 3

( ) { (pCi

mrad-m )

pCi-m PGi-yr

f. Receptor at the " Rocks"; ground-level release conditions: l l

D{3,mc,3 = 4.6E-07

t-0 287 * [(Qi

Dd) (3-7f) 1 3

Ci-yr ) [ (pCi e arad-m ) (arad) = ( PpCi-m3 ) * ( PGi-yr \ B.3-23 ODCM Rev, 16 3.8 METHOD TO CALCUIAT' THE BETA AIR DOSE FROM NOBLE CASES 3.8.1 Method I (Continued) Equations 3-7a through 3-7f can be applied under the following conditions (otherwise justify Method I or consider Method II):

1. Normal operations (nonemergency event), and

2. Noble gas releases via station vents to the atmosphere.

Method IA is implemented by the EMS software as described in Appendix C. Giscous release models are detailed in Section 6.7.3 of the EMS Software R;quirements Specification (Attachment 3 of Appendix C). 3.8.2 Method II Method II consists of the raodels, input data (dose factors) and assumptions in Rsgulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or cesumptions have been identified in the ODCM. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified M;thod I approach as described in the Basec Section 7.2.5, are also applied to Msthod II assessments. Concurrent meteorology with the release period may be utilized for the atmospheric dispersion factor identified in ODCM Equation 7-15, and determined, as indicated in Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. O O B.3-24 ODCM Rev. 16 3.9 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE FROM IODINES, TRITIUM AND PARTICULATES Technical Specification 3.11.2.3 limits the critical organ dose to a member of O the public from radioactive iodines, tritium, and particulates with half-lives greater than 8 days in gaseous effluents to 7.5 arem per quarter and 15 arem per I year per unit. Technical Specification 3.11.4 limits the total body and organ dose to any real member of the public from all station sources (including 5aseous effluents) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year. l Use Method I or Method IA first to calculate the critical organ dose from gaseous effluent releases as it is simpler to execute and more conservative than ., Method II. f Use Method II if a more refined calculation of critical organ dose is needed l (i.e. , Method I or Method IA indicates the dose is greater than the limit) . See Section 7.2.6 for basis. 3.9.1 Method I D,, = (X/Q)$1/(X/Q)dgl

t-* * { (Qi

DFG .)

t (3-8) (area) = ( )/( see) * ( ) * [ (pCi) * ( ) where D., is the critical organ dose from iodines, tritium, and particulates, (X/Q)d23 1 is the 1-hour depleted atmospheric dispersion factor. (X/Q)dgl is the annual average depleted atmospheric dispersion. t-* is a unitiess adjustment factor to account for a release with a total duration of t hours, Qi is the total activity in pCi of radionuclide "i" released to the atmosphere during the period of interest (for strontiums, use the most recent measurement), and DFG , is the site-specific critical organ dose factor for radionuclide "i", 3 see Tables B.1-12, B.1-14, and B.1-15. (For each radionuclide, it is the age group and organ with the largest dose factor.) Incorporating receptor location-specific atmospheric dispersion factors ((X/Q)j@l and (X/Q)dgl) and adjustment factors (t-*) for elevated and ground-level release conditions, and incorporating occupancy factors when applicable (see Section 7.2.7), yields a series of equations by which the critical organ dose can be determined. O . B.3-25 ODCM Rev. 16 l I I 3.9 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE FROM IODINES, TRITIUM AND PARTICULATES 3.9.1 gethod I (Continued)

a. Maximum off-site receptor location, elevated release conditions:

O'1I D,.c 3 = 14. 8

t-o.zs? * { {Qi

DFG1 ,,c.3) (3-8a) 1 I (mrem) = ( )*( ) { (pCi * )

i

b. Maximum off-site receptor location, ground-level release conditions:

D,,(,3 = 17. 7

t-o. sis , { (qt , pygico(s)) ,,

(3-8b) (arem) = ( )*( ) { (pCi * )

c. Science & Nature Center receptor; elevated release conditions:

D,,gc.) = 3.3E-02

t-0 3'8 * { (Qi

DFGiegc3) (3-8c) k (arem) = ( )*( ) { (pCi * )

d. Science & Nature Center receptor; ground-level release conditions:

D,gg,3 = 3. 3E-02

t-0 8'7 * { (Qi

DFG ,gg,3) (3-8d)

(mrem) = ( )*( ){ (pci* ) i O

e. Receptor at the " Rocks"; elevated release conditions:

D,ac,3 = 7.3E-02

t-o.24s * { (Qi

DFG1,ac 3) (3 8e)

(arem) = ( )*( ){ (pCi* )

f. Receptor at the " Rocks"; ground-level release conditions:

D,gg,3 = 8.6E-02

t-o.2sr , p (qt , ppgica(s)) (3-8f) 1 (mrem) = ( )*( ){ (pCi* )

Equations 3-8a through 3-8f can be applied under the following conditions (otherwise, justify Method I or consider Method II):

1. Normal operations (nonemergency event),

2. Iodine, tritium, and particulate releases via station vents to the atmosphere, and

3. Any continuous or batch release over any time period.

B.3-26 ODCM Rev. 16 1 l l 3.9 liETHOD TO CALCUIATE THE CRITICAL ORCAN DOSE FROM 10 DINES, TRITIUM AND PARTICUIATES 3.9.1 Method I (Continued) Method IA is implemented by the EMS software as described in Appendix C. Gaseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.9.2 Method II Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM (see Tables B.7-2 and B.7-3). The critical organ dose will be determined based on the location (site boundary, nearest resident, or fara) of receptor pathways, as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the l t release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose will consider the four age groups independently, and use a shielding factor (Sp) of 0.7 associated with residential structures. O v 1 l B.3-27 ODCM Rev. 16 1 3.10 METHOD TO CALCULATE DIRECT DOSE FROM PLANT OPERATION Technical Specification 3.11.4 restricts the dose to the whole body or any organ to any member of the public from all uranium fuel cycle sources (including direct radiation from station facilities) to 25 mrem in a calendar year (except the thyroid, which is limited to 75 mres). It should be noted that since there are no uranium fuel cycle facilities within 5 miles of the station, only station sources n:ed be considered for determining compliance with Technical Specification 3.11.4. 3.10.1 Method I The direct dose from the station will be determined by obtaining the dose from j TLD locations situated on-site near potential sources of direct radiation, as well c,a chose TLDs near the site boundary which are part of the environmental monitoring program, and subtracting out the dose contribution from background. Additional methods to calculate the direct dose may also be used to supplement the TLD information, such as high pressure ion chamber measurements, or analytical design calculations of direct dose from identified sources (such as solid waste storage facilities). The dose determined from direct measurements or calculations will be related to the nearest real person off-site, as well as those individuals on-site involved in activities at either the Education Center or the Rocks boat landing, to assess the contribution of direct radiation to the total dose limits of Technical Specification 3.11.4 in conjunction with liquid and gaseous effluents. O l l l I f O B.3-28 ODCM Rev. 16 3.11 DOSE PROJECTIONS Technical Specifications 3.11.1.3 and 3.11.2.4 require that appropriate portions of liquid and gaseous radwaste treatment systems, respectively, be used to (O/ reduce radioactive effluents when it is projected that the resulting dose (s) would exceed limits which represent small fractions of the "as low as reasonably achievable" criteria of Appendix I to 10CFR Part 50. The surveillance requirements of these Technical Specifications state that dose projections be performed at least once per 31 days when the liquid radwaste treatment systems or gaseous radwaste treatment systems are not being fully utilized, j Since dose assessments are routinely performed at least once per 31 days to i account for actual releases, the projected doses shall be determined by comparing the calculated dose from the last (typical of expected operations) completed 31-day period to the appropriate dose limit for use of radwaste equipment, adjusted if i appropriate for known or expected differences between past operational parameters and those anticipated for the next 31 days. 3.11.1 Liould Dose Proiections The 31-day liquid dose projections are calculated by the following:

a. Determine the total body Da and organ dose D. (Equations 3-1 and 3-2, respectively) for the last typical completed 31-day period. The last typical 31-day period should be one without significant identified operational differences from the period being projected to, such as full power operation vs. periods when the plant is shut down.

b. Calculate the ratio (R ) of the total estimated volume of batch releases 2

expected to be released for the projected period to that actually ) O released in the reference period. Calculate the ratio (R2) of the estimated gross primary coolant activity c. for the projected period to the average value in the reference period. Use the most recent value of primary coolant activity as the projected value if no trend in decreasing or increasing levels can be determined.

d. Determine the projected dose from:

Total Body: Da ,, - Du, . Rt .R 2 Max. Organ: D. ,, = D. . R t .R The EMS software can also be used to perform monthly projected dose calculations as described in Appendix C. The methodology applied by EMS in projecting liquid doses is outlined in Section 2.7 of Attachment 4 to Appendix C (EMS Technical Reference Manual). 3.11.2 Gaseous Dose Proiections For the gaseous radwaste treatment system, the 31-day dose projections are calculated by the following:

a. Determine the gamma air dose DL, (Equation 3-6a), and the beta air dose p(,

(Equation 3-7a) from the last typical 31-day operating period. B.3-29 ODCM Rev. 16 3.11 DOSE PROJECTIONS 3.11.2 Caseous Dose Proiections

b. Calculate the ratio (R 3) of anticipated number of curies of noble gas to be released from the hydrogen surge tank to th:s atmosphere over the next 31 days to the number of curies released in the reference period on which the gamma and beta air doses are based. If no differences between the reference period and the next 31 days can be identified, set R3 to 1.

c. Determine the projected do e from:

Gamma Air: DL, p = DL, . R3 Beta Air: D{, y . D[, . R3 For the ventilation exhaust treatment system, the. critical organ dose from iodines, tritium, and particulates are projected for the next 31 days by the following:

a. Determine the critical organ dose D., (Equation 3-8a) from the last typical 31-day operating period. (If the limit of Technical Specification 3.11.2.4.c. (i.e. , 0.3 mrers in 31 days) is exceedad, the projected controlled area annual total effective dose equivalent from all station sources should be assessed to assure that the 10CFR20.1301 dose limits to members of the public are not exceeded.)*

b. Calculate the ratio (R 4) of anticipated primary coolant dose equivalent I-131 for the next 31 days to the average dose equivalent I-131 level '

during the reference period. Use the most current determination of DE I-131 as the projected value if no trend can be determined.

c. Calculate the ratio (R )3 of anticipated primary system leakage rate to the average leakage rate during the reference period. Use the current value of the system leakage as an estimate of the anticipated rate for the next 31 days if no trend can be determined.

d. Determine the projected dose from:

Critical Or5an: D , p - D., . R 4 . R3 The EMS software can also be used to perform monthly projected dose calculations as described in Appendix C. The methodology applied by EMS in projecting gaseous dose is outlined in Section 3.8 of Attachment 4 to Appendix C (EMS Technical Reference Manual). f 9 B.3-30 ODCM Rev. 16 3.11 DOSE PROJECTIONS 3.11.2 Cascous Dose Proiections (Continued) Note: This action is based on the assumption that tritium is the controlling nuclide for whole body exposures through the inhalation pathway. Maximum annual average on-site X/Q's for station affluent release points are approximately 100 times the values used for the site boundary dose calculations. However, the site boundary doses calculated by the ODCM for iodines, tritium, and particulates with half lives greater than 8 days, includes all potential off-site exposure pathways. For tritium, the inhalation pathway only accounts for 10% of the total dose contribution being calculated. As a result, if the monthly calculation indicates that the site boundary maximum organ dose reached 0.3 mrem, the on-site maximum dose due to inhalation would be approximately 3.0 area for this period. If this were projected to continue for a year with a 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months occupancy factor applied, the projected inhalation whole body dose would be approximately 8 mres, or 8% of the 10CFR20.1301 limit. This is a reasonable trigger value for the ne d to consider the dose contribution from all station sources to members of the public in controlled areas. n O B.3-31 ODCM Rev. 16 j 4.0 RADIOlhCICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environaental monitoring stations are listed in Table B.4-1. (d,i The locations of the stations with respect to the Seabrook Station are shown on the maps in Figures B.4-1 to B.4-6. Direct radiation measurements are analysed at the station. All other radiological analyses for environmental samples are performed at the Yankee j Environmental Laboratory. The Yankee Environmental Laboratory participates in the U.S. Environmental Protection Agency's Environmental Intercomparison Studies Program for all relevant species in an aqueous (water) matrix. An independent vendor (Analytics) supplies the remaining cross check samples. These samples are presented on an air filter and in milk and water matrices. Pursuant. to Specification 4.12.2, the land use census will be conducted "during the growing seacon" at least once per 12 months. The growing season is defined, for the purposes of the land use census, as the period from June 1 to October 1. Tbe method to be used for conducting the census will consist of one or more of the following, as appropriate: door-to-door survey, visual inspection from roadside, aerial survey, or consulting; with local agricultural authorities. Technical Specification 6.8.1.3 requires that the results of the Radiological Environmental Monitoring Program he sammarized in the Annual Radiological Environmental Operating Report "in the format of tha table in the Radiological Assessment Branch Technical Position, Revision 1, 1979." The. general table format will be used with one exception and one clarification, as follows. The mean and range values will ba based not upon deteerable measurements only, as specified in the NRC Branch Technical Position, but up<n all measurements. This will prevent the positive bias associated with the calculacion of the mean and range based upon detectable measurements only. Secondly, the Lower Limit of Detection column will ] specify the LLD required by ODCM Table A.5-2 for that radionuclide and sample ' medium. /De U l B.4-1 ODCM Rev. 17 l l l TABLE B.4-1 l RADIOIDCICAL ENVIRONMENTAL MONITORING STATIONS (*) Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Samele and Desirnated Code Containment (km) the Plant

1. AIRBORNE (Particulate and Radioiodine)

AP/CF-01 PSNH Barge 2.7 ESE Landing Area AP/CF-02 Harbor Road 2.7 E AP/CF-03 SW Boundary 0.8 SW AP/CF-04 W. Boundary 1.0 W AP/CF-05 Winnacunnet H.S.0) 4.0 NNE AP/CF-06 Georgetown 24.0 SSW Substation (Control) AP/CF-07 PSNH Substation (b) 5.7 NNU AP/CF-08 E6H Substation 0) 3.4 SSE

2. WATERBORNE

a. Surface US-01 Hampton-Discharge Area 5.3 E US-51 Ipswich Bay (Control) 16.9 SSE

b. Sediment SE-02 Hampton-Discharge Area O) 5.3 E SE-07 Hampton Beach 0) 3.1 E SE-08 Seabrook Beach 3.2 ESE SE-52 Ipswich Bay (Control)*) 16.9 SSE SE-57 Plum Island Beach 15.9 SSE (Control)(b)

3. INGESTION l l

a. Milk TM-04 Salisbury, MA 5.2 SW l l TM-08 Hampton Falls, NH 4.3 NNW {

TM-09 Hampton, NH 5.5 NNW l TM-15 Hampton Falls, NH 7.0 NW j TM-16 Kensington, NE S) 7.7 UNW I TM-20 Rowley, MA (Control) 16.3 S l TM-21 North Andover, MA O) 29.0 SU

b. Fish and Invertebrates (*)

FH-03 Hampton - Discharge 4.5 ESE Area FH-53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 5.5 E , j Area HA-54 Ipswich Bay (Control) 17.2 SSE l MU-06 Hampton - Discharge 5.2 E j Area l j l MU-09 Hampton Harbor O) 2.6 E f MU-56 Ipswich Bay (Control) 17.4 SSE l l MU-59 Plum IslandO) 15.8 SSE e i l B.4-2 ODCM Rev. 17 l l l l l ) u j L { 1 TABLE B.4-1 RADIOIDGICAL ENVIRONMENTAL MONITORING STATIONS (*) (Continued) O V Exposure Distance From Direction Fron l l Pathway and/or Sample Location Unit 1 Direction From ( Sample and Desienated Code Gontairunent (km) the Plant ( 4. DIRECT RADIATION j TL-1 Brimmer's Lane, 1.1 N Hampton Falls TL-2 Landing Rd., Hampton 3.2 NNE l TL-3 Clade Path, Hampton 3.1 NE Beach TL 4 Island Path, Hampton 2.4 ENE Beach TL-5 Harbor Rd. , Hampton 2.7 E Beach TL-6 PSNH Barge Landing 2.7 ESE l Area l TL-7 Cross Rd. , Seabrook 2.6 SE Beach TL-8 Fara Lane, Seabrook 1.1 SSE , l TL-9 Fara Lane, Seabrook 1.1 S TL-10 Site Boundary Fence 1.0 SSW i l TL-11 Site Boundary Fence 1.0 SW TL-12 Site Boundary Fence 1.0 WSW TL-13 Inside Site Boundary 0.8 W O TL-14 TL-15 Trailer Park, Seabrook Brimmer's Lane, Hampton Falls 1.1 1.4 WNW NW TL-16 Brimmer's 14ne. 1.1 NNW Hampton Falls l I TL-17 Sorch Rd., N. Hampton 7.9 N TL-18 Mill Rd. , N. Hampton 7.6 NNE TL-19 Appledore Ave., 7.9 NE l N. Hampton TL-20 Ashworth Ave., 3.4 ENE l Hampton Beach TL-21 Route 1A, Seabrook 2.7 SE ! Beach i TL-22 Cable Ave., 7.6 SSE Salisbury Beach , i TL-23 Ferry Rd., Salisbury 8.1 S l TL-24 Ferry Lots Lane, 7.2 SSW Salisbury l TL-25 Elm St. , Amesbury 7.6 SW l TL-26 Route 107A, Amesbury 8.1 WSW i l l O B.4-3 ODCM Rev. 16 l 1 i TABLE B.4-1 RADIOIDGICAL ENVIRONMENTAL MONITORING STATIONS (*) l (Continued) Exposure Distance From Direction From Pathway and/or Sample location Unit 1 Direction From - l Sannle and Desimated Code Containment (km) the Plant l TL-27 Highland St. , 7.6 W l S. Hampton TL-28 Route 150, Kensington 7.9 WNW l l TL-29 Frying Pan Lane, 7.4 NW Hampton Falls , TL-30 Route 27, Hampton 7.9 NNW l l TL-31 Alumni Drive, Hampton 4.0 NNE l Seabrook Elementary School 1.9 I TL-32 S 9.7 l TL-33 Dock Area, Newburyport S ! TL-34 Bow St. , Exeter 12.1 NW TL-35 Lincoln Ackerman School 2.4 NNW TL-36 Route 97 Georgetown 22.0 SSW l (Control) TL-37 Plaistow, NH (Control) 26.0 WSW TL-38 Hampstead, NH (Control) 29.0 W TL-39 Fremont, NH (Control) 27.0 UNW l l TL-40 Newmarket, NH (Control) 24.0 NNW l TL-41 Portsmouth, NH 21.0 NNE (Control)*) Ipswich, MA (Control)N l TL-42 27.0 SSE I (a) Sample locations are shown on Figures B.4-1 to B.4-6. (b) This sample location is not required by monitoring program defined in Part A of ODCM; program requirements specified in Part A do not apply to samples taken at this location. 1 (c) Samples will be collected pursuant to ODCM Table A 5-1. Samples are not required from all stations listed during any sampling interval (FH - Fish; l HA - Lobsters; MU - Mussels). Table A.5-1 specifies that "one sample of three commercially and recreationally important species" be collected in the vicinity of the plant di.ccharge area, with similar species being collected at a control location. (This wording is consistent with the NRC Final Environmental Statement for Seabrook Station.) Since the discharge area is off-shore, there is a great number of fish species that could be considered commercially or recreationally important. Some are migratory (such as striped bass), making them lees desirable as an indicator of plant-related radioactivity. Some pelagic species (such as herring and mackerel) tend to school and wander throughout a large area, sometimes making catches of significant size difficult to obtain. Since the collection of all specie 9 would be difficult or impossible, and would provide unnecessary redundsney in terms of monitoring i.mportant pathways to man, three fish and invertebrate species have been specified as a minimum requirement. Samples may include marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish, such as flounder or hake. Several similar species may be grouped together into one sample if sufficient sample mass for a single species is not available after a reasonable effort has been made (e.g., yellowtail flounder and winter flounder). B.4-4 ODCM Rev. 16 FIGURE 5.4-1 BAgtOtocTCAL EN7T10NMErrAI MONTTORINC IDCATIONS VITHIN 4 KITEMETElts OF SEABROOK STATION O f4 b f \ ^ %~Q / 1 $M % sinIG J._ i %f AP/C A O Ap/CF-04 A ~ i RAMPTONgAns0R( . , n ( AP/CF-01'A s ~ w j ' / SE-US A 1 %, 5h 5 500 AP/CF-48. A #' 5 O 1000

5 k f 4 :

METERS 74 $ I ( \ / fs I 1 0 B.4-5 ODCM Rev. 17 FIGURI a. 4 2 RADTOTECTCAL ENVIRONMDTTAL h6N11GRTNC IDCATTONS BETwtu 4 YTILhurxS AND 12 KTL0ku rxS FROM SEARROOK STATTON O O o 5 _~ [' KILONETES E M E N RYE BEACH TM-09 A -- TM-15 A SEEEN1.ARGEMENTINFkGURE8.4-1 A AP/CF 45 I I 8 TM-16 A ' e-- IfMPTCN BEACH i lASE-07 SEAsa00K 5 ATION a " DISCHLaGE SITE WS-01 l SE-02 Iti-06 ] ..___. ._, ;+ -Suanoce ras n-04 nuca i s.i, . .- , l \. . t 8..}QA = l ,e al a*** Hf $AdSBURY BEACH e P O ATLANTIC OCUM l l s.4-6 oocM 2ev. 17 g l FIGURE B.4-3 RADIOIDCICAL ENVIPONMENTAL MONITORING IDCATIONS OUTSIDE 12 KILOMETERS OF SEABROOK STATION O \f o 5 10 15 I KILOMETERS YORK e OffRHAM e > UWR ! NEWMARKET e RT5MOUT11e _. O \ , EPPING

\@

t I i SEE ENLARGEMENT IN FIGURE l ' 8.4-Z --48 HAMPTON 3 I I I e , 8 i 8 l I SEABROOKSTATION) HAMPTON H#JtSOR KINGSTOL e , "~,- 'Y [\t DISOIARGE SITE i e SALI58URY f 3 < p s"AMESSURY g e ' / i I PLAISTOW e n / t .

p. a

. - .,,,,N. H' I

4"y'# - NEWBURYPORT e .) 8 A M IC OCEAN

/ ! HAVDMILLe _____________(~___i ,A $E-57 ! l PLtm ISLAND , . ; , i TM-20 FM-53 AP/CF-06 A A SE-52 METHUEN e A WS-51

LAW M CE IPSWICH BAY A MU-56 IPSWICH e NA GLOUCESTER O ODCM Rev. 16 B.4-7

FIGURE B.4-4 DIRECT RADIATION MONITORING IDCATIONS VITHIN 4 KILOMETERS OF SEABROOK STATION s O NNW N NNE A TL-2 NE \ - NATL-35 - - l A D3 i I A R-4 ENE gg a A TL-16 7 9# A TL-1 47 ' WNW TL-14 A g sm % i E " k TL-5 A R- 3 ^ HAMPTON RARSOR ( $a l TL-12 A ,4 TL-11 A t g i TL-9 'i' -/ . ,3, / ATL-7 TL-32 A *" = Su !$ g o 5 3 M / o 500 1000

1$

47TL- l g SSW SSE SE S B.4-8 ODCM Rev. 16 MM DIRECT RADIATION MONITORING IDCATIONS BETVEEN 4 KIIDMETERS AND 12 KIIDMETFRR FROM SEABROOK STATION O H = NNW NNE E' 0 $ KILbERS e NW 5 & NE A TL-34 N ! MH es h # "A RYE BEACM A TL-17 A TL-30 n-18 A TL-19 [ A TL-29\ T - WNW , \ ENE SEE BLAAGEMENT IN FIGURE B.4-4 ,3 i n z. ,----r-- ' o W A TL-17 l, $USM RAT,IM a i i OISCMAGE SITE - I , . %., i j N.' SEA 8R00X SEACM TL-z6 i 'N '. s ,,. t--- 9, . WsW ' 7\k 5 53URY ,Br.ACH TL-24 A n-zz A) N O

*'A MUREMac_ g6 ,

SE E~33 A ATLANTIC OCEAM SW SSW / 5 SSE \ O ODCM Rev 16 B.4-9 FICURE B.4-6 DIRECT RADIATION MONITGiNG IACATIONS OUTSTDE J2 KILOMETERS OF SEABROOK STATION O 0 5 10 NNW 15 N i. / I NNE v [ l KILOMETIRS NW a YORX J e e j . 9 " NE CURNAM e 0j 4yfg-TL-40 A ( xa^;a E m nG s . x,,xET . v4RT5acutae 10,n.,/tt-'t - .\ . s , $\.$ ! WNW __ ------ --- , *? \* ENE 8 FREMONT l ' N TL-398 e e EXETER SEE BLARGZMGT IN FIGURE J 8.4-5 HAMPTON i e' , I I w KINGSTCN* ', SEA 8 ROOK, STATIONl , sus 00K e a E g I . DISCHAltGE SITE TL-38 A ,8 . *' K/4. ,gggggggy I l 4AME38URY # PLAISTOW e. , t ESE TL-37 A / g,g' ! / [I */ / NEW8UR ORT . ' ATLANTIC OCEAN / %'p'f- _ _ ---- I NSN I HAVERMILLe PLUM 13tMt0 .I ' ETHus TL-36 A eNE IP5WICH 8AY gg IP5WICH e gTL-42 GLOUCEST U S$W S SSE \_ O B.4 10 ODCM Rev. 16 I 5.0 SETPOINT DETERMINATIONS ,m Chapter 5 contains the methodology for the calculation of effluent monitor setpoints to implement the requirements of the radioactive effluent monitoring systems Technical Specifications 3.3.3.9 and 3.3.3.10 for liquids gases, respectively. Example setpoint calculations are provided for each of the required effluent monitors. , l 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS Technical Specification 3.3.3.9 requires that the radioactive liquid effluent instrumentation in Table 3.3-12 of the Technical Specifications have alarm setpoints i in order to ensure that Technical Specification 3.11.1.1 is not exceeded. Technical Specification 3.11.1.1 limits the activity concentration in liquid effluents to the appropriate MPCs in 10CFR20 and a total noble gas MFC. 5.1.1 Liould Waste Test Tank Monitor (RM-6509) The liquid waste test tank effluent monitor provides alarm and c tomatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. It is also used to monitor discharges from various waste sumps to the environment. 5.1.1.1 Method to Determine the Setroint of the Liould Waste Test Tank Monitor (RM-6509) The alarm setpoint is based on ensuring that radioactive effluents in liquid A waste are in compliance with Technical Specification limits which are based on the Q concentration limits in Appendix B to 10CFR20. The alarm point depends on available dilution flow through the discharge tunnel, radwaste discharge flow rate from the test tanks, the isotopic composition of the liquid waste, and the monitor response efficiency and background count rate applicable at the time of the discharge. The alarm / trip setpoint is determined prior to each batch release taking into account current values for each variable parameter. The following steps are used in determining the monitor setpoint: First, the minimum required dilution factor is determined by evaluating the isotopic analysis of each test tank to be released along with MFC requirements for each radionuclide. The most recent analysis data for tritium and other beta emitters that are analyzed only monthly or quarterly on composite samples can be used as an estimate of activity concentration in the tank to be released. For noble gases, the Technical Specification limit (T.S.3.11.1.1) is defined as 2E-04 pCi/ml total for all dissolved and entrained gases. Therefore, l Dr ={ # or { fg, whichever is larger. (5-3) l Where: DFm - Minimum required dilution factor necessary to ensure that the sum of the ratios for each nuclide concentration divided by its MFC value is not greater than 1 (dimensionless). ( \ B.5-1 ODCM Rev. 17 l l 5,1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS l 5.1.1.1 Method to Determine the Setroint of the Liould Waste Test Tank Monitor (RM-6509) (Continued) C1 - Activity concentration of each radionuclide "i" (except noble gases) determined to be in the test tank (pci/ml). This includes tritium and other non gamma emitting isotopes either measured or estimated from the most recent composite analysis. j l' C, - The sum of all dissolved and entrained noble gases identified in each test tank (pCi/ml). As a conservative limit, each of the potential 20 noble gases can be limited to an individual concentration limit of IE-5pCi/ml. MPC i - The concentration limit (above background) at point of discharge to the environment for radionuclide "i" t.aken from 10CFR20, Appendix B, Table II, Column 2 (pci,.d1 for all nuclides other . than noble gases. See ODCM, Appendix B, for a listing. In the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture or a mixture known not to contain certain radionuclides as given in 10CFR20, Appendix B, notes. 2E-04 - The total dissolved and entrained noble gas Technical Specification concentration limit in liquid effluents from the plant (pCi/ml). Next, the available dilution flow through the discharge tunnel (Fe), or a G, conservative estimate for it, is divided by the minimum dilution factor (DFe ) to determine the maximum allowable discharge flow rate (F ,) that the test tanks could be released at without exceeding the MPC limits assuming no additional radioactive flow paths are discharging at the time of release of the test tanks. Therefore, = # l F""" DF,u l Where: F.,x - The maximum allowable discharge flow rate from the test tank past the monitor which would equate to the Technical Specification concentration _ limit for the radioactivity mixture determined to be in the test tank (gpm). Fd - The actual or conservative estimate of the flow rate out of the discharge tunnel (gpm). The selection of the actual discharge flow rate (F,) from the test tanks compared to the maximum allowable discharge rate must satisfy the following: l F, 5 F , X fst B 5-2 ODCM Rev. 17 j 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS l p 5.1.1.1 Method to Determine the Setnoint of the Liould Waste Test Tank Monitor (RM-6509) (Continued) l where the fss represents an administrative fraction of the maximum allowable l discharge flow from the test tanks. This fraction provides additional margin in l meeting MFC limits for non-gamma emitters (such as tritium) at the discharge point j to the ocean when other flow paths may contribute to the total site release at the ' time of tank discharges and minimum dilution flow conditions exist. With the above conditions on discharge and dilution flow rates satisfied, the I alarm / trip setpoint for the monitor which corresponds to the maximum allowable ! concentration at the point of discharge (conservatively assuming that any change in )j the expected gamma activity in a test tank is also reflective of the same change in non gamma emitters, such as tritium) is determined as follows: f3 X X[Cyf (5-1) l R,,e = f Where: Rsetytnt - The maximum allowable alarm / trip setpoint for an instrument response (pCi/ml) that ensures the limiting concentration at l the point of discharge is not exceeded, f3 - The fraction of the total ,:ontribution of MPC at the discharge point to be associated with the test tank effluent pathway, where fz. fs, and f. are the fractions for the p (j Turbine Building Sump, Steam Generator Blowdown, and Primary Component Cooling pathways contributions to the total, respectively (f 2+f +f 3+f. s 1). Each of the fractions may be conservatively set administrative 1y such that the sum of the fractions is less than 1. This additional margin can be used to account for the uncertainty in setpoint parameters such as estimated concentration of non gamma emitters that are based on previous composite analyses of the vaste ! stream. 5.1.1.2 Liould Waste Test Tank Monitor Setooint Examole l The radioactivity concentration of each radionuclide, C , in the waste test 1 tank is determined by analysis of a representative grab sample obtained at the radwaste sample sink, and analyzed prior to release for gamma emitters, or as part of a composite analysis for non gamma emitters. This setpoint example is based on the following data: l 1 Ci (pCi/ml) MPCi (pCi/ml) l Cs-134 2.15E-05 9E-06 l l Cs-137 7.48E-05 2E 05 Co-60 2.56E-05 3E-05 l H-3 1.50E-01 3E-03 l i m l The minimum required dilution factor for this mix of radionuclides is: ll B.5-3 ODCM Rev. 17 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS l 5.1.1.2 Liouid Waste Test Tank Monitor Setnoint Exarnie (Continued) c, 2.1ss-os . v.481-Os . 2.s61-Os . 1.sor-01 . s, j ,,, . g MFCs 9 E-06 2E-05 3E-05 3 E-03 The release flow rate (F.) from the waste test tanks can be set between 10 and f j 150 gym. The cooling water tunnel discharge dilution flow rate (F,) can vary from ' 8,800 to 412,000 gpm depending on the operating status of the plant. In this example, if the dilution flow (F,) is taken as 412,000 gpm, the maximum allowable discharge rate (F ) is: F"" = DF 1, 412,000 s7 = 7228 gpm With the selected release rate from the test tank set at 150 gpm, and the administrative flow fraction (fst) assumed in this example to be 0.7, the condition for the Technical Specification concentration limits is met since: F, (equal to 150) < F., (equal to 7228 gpm) X fss (set at 0.7) 150 < 5060 l and the monitor response due to the mix of the gamma emitters is: l 1 Cyi (pci/ml) l Cs-134 2.15E-05 l Cs-137 7.48E-05 Co-60 2.56E-05 { cri = 1.22E-04pci/ml Under these conditions, the alarm / trip setpoint for the liquid radwaste discharge monitor is: l Rupe "f t X

r. y X { cyl (5-1) 7-l pCi/ml () () pCi/ml O

B.5-4 ODCM Rev. 17 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 5.1.1.2 Liould Umste Test Tank Monitor setnoint sv== ale (Continued) 4 Row x 1.22E-04 = 0.4 X l 50 5 - 2.35E-03 Ci/ml In this example, the alarm / trip setpoint of the liquid radwaste discharge monitor can be put at 2.35E-03 pCi/ml above background. In this example, it is assumed that the test tank release pathway will be limited to only 40% of the total site discharge allowable concentration. 5.1.2 Turbine Buildine Drains Liould Effluent Monitor (RM-6521) The Turbine Building drains liquid affluent monitor continuously monitors the Turbine Building sump effluent line. The only sources to the Sump Effluent System are from the secondary steam system. Activity is expected in the Turbine Building Sump Effluent System only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, with reduced activity from decay and dilution. The Turbine Building drains liquid effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CPR20, Appendix B, Table II, Column 2 to the environment. The alarm setpoint for this monitor will be determined using the same method as that of the liquid waste test tank monitor if the total sump activity is greater than 10 percent of MPC, as determined by the most recent grab sample isotopic analysis. If the ( total activity is less than 10 percent of MPC, the setpoints of RM-6521 are calculated as follows: High Trip Monitor l Setpoint (pci/al) - f 2(DF') (" unidentified mix MPC" (pCi/ml)) (5-21) where: pp. _ Circulating water flow rate (gpm) Flow rate pass-monitor (gpm) unidentified mix MPC - most restrictive MPC value (pci/ml) for an unidentified mixture or a mixture known not to contain certain radionuclides as given in 10CFR20, Apper. dix B, Notes. f2 - 1 - (ft + fs + f.); where the f values are described above. In addition, a warning alarm setpoint can be determined by multiplying the high trip alarm point by an administratively selected fraction (as an example, 0.25). Warning Alarm - High Trip (5-22) Monitor Setpoint ( ) (0.25) (pCi/ml) M0"It I 88tP 1"U O B.5-5 ODCM Rev. 17 i 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 6.1.3 Steam Generator Blowdown Liould Samole Monitor (RM-6519) The steam generator blowdown liquid sample monitor is used to detect abnormal cetivity concentrations in the steam generator blowdown flash tank liquid discharge. l The alarm setpoint for the steam generator blowdown liquid sample monitor, when liquid is to be discharged from the site, will be determined using the same approach as the Turbine Building drains liquid effluent monitor. For any liquid monitor, in the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MFC for an " unidentified" mixture given in 10CFR20, Appendix B notes. 5.1.4 PCCW Head Tank Rate-of-Chance Alarm Setooint A rate-of-change alarm on the liquid level in the Primary Component Cooling Water (PCCW) head tank will work in conjunction with the PCCV radiation monitor to clert the operator in the Main Control Room of a leak to the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint is selected based on detection of an activity level equivalent to 10-s pCi/ml in the discharge of the Service Water System. The activity in the PCCW is determined in accordance with the liquid sampling and analysis program described in Part A, Table A.3-1 of the ODCM cnd is used to determine the setpoint. The rate-of-change alarn setpoint is calculated from: RC,,g - 1x10-e , ggy , (5-23) gal mi (gal) hr ,,,(pCi) al (E)(%) where: RC ,s - The setpoint for the PCCW head tank rate-of-change alarm (in gallons per hour). lx10-8 - The minimum detectable activity level in the Service Water Syste due to a PCCW to SUS leak (pCi/ml). SWF - Service Water System flow rate (in gallons per hour). PCC - Primary Component Cooling Water measured (decay corrected) gross radioactivity level (pCi/ml). As an example, assume a PCCW activity concentration of lx10-s Ci/ml with a cervice water flow rate of only 80 percent of the normal flow of 21,000 gpm. The rate-of-change setpoint is then: l RC,,,- lx10-s pCi . 1.0x10 8 gph (1/1x10-5 pCi) ml ml RC,,, - 1000 gph e i B.5-6 ODCM Rev. 17 1 I 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 5.1.4 PCCW Head Tank Rate-of-Channe Alarm Setnoint (Continued) r As a result, for other PCCW activities , the RC,,s which would also relate to a detection of a minimum service water concentration of lx10-e pCi/ml can be found 7 from: ] 1x10-5 e pCi/a1

1000 gph (5-24)

RC*** PCC 5.1.s PCCW Radiation Monitor ; The FCCW radiation monitor will alert the operator in the Main Control Room of a leak to the PCCW System from a radioactively contaminated system. The PCCW radiation monitor alarm is based on a trend of radiation levels in the PCCW System. The background radiation of the PCCW is determined by evaluating the radiation levels over a finite time period. The alert alarm setpoint is set at 1.5 x background, and the high alarm setpoint is set at 2 x background, per Technical Specification Table 3.3-6. l l l l l I l l O B.5-7 ODCM Rev. 17 l r l l 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS l Technical Specification 3.3.3.10 requires that the radioactive gaseous sffluent instrumentation in Table 3.3-13 of the Technical Specifications have their clarm setpoints set to insure that Technical Specification 3.11.2.1 is not exceeded. 5.2.1 Plant Vent Vide-Rance Gas Monitors (RM-6528-1.2 and 3) The plant vent wide-range gas monitors are shown on Figure B.6-2. 5.2.1.1 Method to Determine the Setooint of the Plant Vent Vide Ranee Cas Monitors (RM-6528-1.2 and 3) The maximum allowable setpoint for the plant vent wide-range gas monitor (readout response in pCi/sec) is set by limiting the off-site noble gas dose rate to the total body or to the skin, and is denoted R .spoing. R,,tpoing is the lesser of: Ra = 588 (5-5) 3 pCi/see - ( mrem-pCi-m ) g pCi-yr) 3 yr pci-sec mrem-m and: P%in - 3,000 (5-6) pCi/sec - ( ****) ( arem-sec pCi-yr ) yr where: Re - Response of the monitor at the limiting total body dose rate (pci/sec) i 3 500 gmrem pci-m ) 588 - (lE+06) (8.5E-07) yr-pCi-sec I 500 - Limiting total body dose rate (arem/yr) lE+06 - Number of pCi per pCi (pCi/pci) l 8.5E--07 - (X/Q)1, maximum off-site long-term average gamma atmospheric j dispersion factor for primary vent stack releases (sec/m8 ) DFB, - Composite total body dose factor (arem-m3 /pCi-yr) l B.5-8 ODCM Rev. 17 1 _____-____________._______j i 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS f' 5.2.1.1 Method to Determine the Servoint of the Plant Vent Wide Ranze Gas Monitors l l (}f (RM-6528-1.2 and 3) (Continued) - E ki DFB i (5 7) E Q1 l Q1 - The release rate of noble gas "i" in the mixture, for each noble gas identified in the off-gas (pCi/sec) l DFB i Total body dose factor (see Table B.1-10) (arem-m3 /pci-yr) Roa - Response of the monitor at the limiting skin dose rate (pci/sec) 3,000 - Limiting skin dose rate (arem/yr) DF', - Composite skin dose factor (arem-sec/pCi-yr) E ki DF'i (5-8) [ $1 DF'i - Combined skin dose factor (see Table B.1-10) -/N (mrem-sec/pci-yr) The following setpoint example for the plant vent wide range gas monitors demonstrates the use of equations 5-5 and 5-6 for determining setpoints. 1 This setpoint example is based on the following data (see Table B.1-10 for DFBi and DF"3): DFB i DF's j Qi (d) sec ("I'"~"8pCi-yr ) ( arem-sec pCi-yr ) i Xe-138 1.03E+04 8.83E-03 1.20E-02 Kr-87 4. 73::+02 5.92E-03 1.38E-02 Kr-88 2.57E+02 1.47E-02 1.62E-02 Kr-85m 1.20E+02 1.17E-03 2.35E-03 Xe-135 3.70E+02 1.81E-03 3.33E-03 i Xe-133 1.97E+01 2.94E-04 5.83E-04 B.5-9 ODCM Rev. 17 l I 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS l 5.2.1.1 Method to Determine the Setooint of the Plant Vent Wide Rance Gas Monitors fRM-6528-1.2 and 3) (Continued) DFB, - i i (5 7) b Di ) l l l { Qi DFB i - (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03) + (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03) + (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) - 9. 83E+01 (pCi-mreta-m 8 /sec-pCi-yr) 5.2.1.2 Plant Vent Wide Rance Gas Monitor Setnoint Example { Qi - 1. 03 E+04 + 4. 7 3 E+02 + 2 . 57 E+02 + 1.20E+02 + 3.70E+02 + 1. 97E+01 - 1.15E+04 pCi/sec DFB, - 9.83E+01 1.15E+04 - 8.52E-03 (mrem-m3 /pCi-yr) Re - 588 (5-5) ~ (8.52E-03) - 6.90E+04 pCi/sec O B 5-10 ODCM Rev. 17 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS 5.2.1.2 Plant Vent U1de Ranee Gas Monitor Setnoint Examnle (Continued) and next; DF', - (5-8) [ 41 { Qi DF's - (1.03E+04)(1.20E-02) + (4.73E+02)(1.38E-02) + (2.57E+02)(1.62E-02) + (1.20E+02)(2.35E-03) + (3.70E+02)(3.33E-03) + (1.97E+01)(6.83E-04) - 1.38E+02 (pci-arem-sec/see-pCi-yr) pp. ,1.36E+02 1.15E+04 - 1.18E-02 (arem-sec/pCi-yr) Rai - 3,000 (5 6) l - (3,000) ((l,lgE-02) - 2.54E+05 pCi/see The setpoint, Rmpas , is the lesser of Ru, and Re. For the noble gas mixture in this example Ru, is less than Raa, it.dicating that the total body dose rate is more restrictive. Therefore, in this example the plant vent wide-range gas monitors should each be set at no more than 6.90E+04 pCi/see above background, or at some administrative fraction of the above value. In the event that no activity is expected to be released, or can be measured in the system to be vented, the gaseous monitor setpoint should be based on Xe-133. 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS 5.2.2 Waste cas System Monitors (RM-6504 and RM-6503) Prccess radiation monitors in the waste gas system provide operational information on the performance of the system before its discharge is combined and diluted with other gas flows routed to the plant vent.for release to the environment. B.5-11 ODCM Rev. 17 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS 5.2.2 Waste Gas System Monitors (RM-6504 and RM-6503) (Continued) The setpoints for the waste gas system monitors are administrative 1y set as small multiples of the expected activity concentration to provide operational control over unexpected changes in gas discharges from the system. Typically, the alert alarm setpoint for both monitors is placed at 1.5 times the expected activity concentration passing the monitor, with the high alarm trip set at 2 times the expected concentration flow. Under all conditions, the maximum allowable alarm trip shall not exceed a 8 concentration equivalent to 62.5 uCi/cm . This concentration limit, based on system design flow of 1.2 cfa, assures that any release from the waste gas system to the plant vent will not exceed the site boundary dose rate limits of Technical Specification 3.ll.2.1.a. 5.2.3 Main Condenser Air Evacuation Monitor (RM-6505) The process radiation monitor on the main condenser air evacuation system provides operational information about the air being discharged. The discharge occurs either directly from the turbine building during start up (hogging mode) or through the plant vent during normal operations. This process monitor is also used as an indicator of potential releases from the Turbine Gland Seal Condenser exhaust. Early indications of a potential release (i.e., monitor count rate at twice the normal background) should be evaluated by collecting a grab sample of the exhausts from both the main condenser and the Turbine Gland Seal Condenser. The operational setpoints for the air evacuation monitor are administrative 1y set as small multiples of the expected background response of the detector to provid9 operational control over unexpected changes in the activity discharged from the system. Typically, the alert setpoint is 1.5 times background, with the high alarm set at 2 times background. MnNm allowable setpoint determinations assure that the site boundary dose rate limits of Technical Specification 3.ll.2.1.a will not8 be exceeded. For a typical air evacuation detector efficiency of 6.0E+05 cpm-cm /pC1, flow rates of 10 and 10,000 cfm for the normal and hogging modes of operation, respectively, and assuming that all the response is due to the most restrictive noble gas (Kr-89), the difference between the stack release and ground level release pathway setpoints for the two modes of operation (normal power and startup, respectively) are seen to be about three orders of magnitude. This example also assumes 670 lbs/ hour of steam flow through the Turbine Gland Seal System,1.5E+07 lbs/ hour of steam flow to the main condenser, and that the Turbine Gland Seal Condenser exhaust flow rate of 1,800 cfm goes directly to the Turbine Building Vents (does not directly pass RM-6505) . For these conditions, the maximum allowable als.rm should not exceed 3.2E+06 cpm when exhausting to the plant vent (assumes an administrative limit of 70% of the calculated value to account for potential contributions from the Turbine Gland Seal Condenser exhaust). Under hogging mode operations, the maximum allowable alarm should not exceed 1.4E+02 cpm (assumes an administrative limit of 15% of the calculated value to account for potential contributions form the plant vent). The maximum allowable setpoints during startup and normal power operations may be recalculated based on identified changes in detector efficiency, discharge flow rate, radionuclide mix distribution, or administrative apportionment of potential contributions from the plant vent and ground level release points following the methods identified in $8.5. B.5-12 ODCM Rev. 17 l 1 b ( l 6.0 LIOUID AND CASEOUS EFFLUENT STREAMS. RADIATION MONITORS AND RADVASTE TREA*IMENT SYSTEMS O Figure B.6-1 shows the liquid effluent streams, radiation monitors and the Q appropriate Liquid Radwaste Treatment System. Figure B.6-2 shows the gaseous ) effluent streams, radiation monitors and the appropriate Gaseous Radwaste Treatment System. For more detailed information concerning the above, refer to the Seabrook Station Final Safety Analysis Report, Sections 11.2 (Liquid Waste System), 11.3 (Gaseous Waste System) and 11.5 (Process and Effluent Radiological Monitoring and ; Sampling System). l The turbine gland seal condensar exhaust iodine and particulate gaseous releases will be determined by continuously sampling the turbine gland seal condenser exhaust. The noble gas releases will be determined by periodic noble gas grab samples. A ratio of main condenser air evacuation exhaust and turbine gland i seal condenser exhaust noble gas will be determined periodically. r I l O I l l l l i l l l I V B.6 1 ODCM Rev. 17 FIGURE B.6-1 LIOUID EFFLITENT STREAMS. RADIATION MONITORS. AND RADUASTE TREATMENT SYSTEM AT SEABROOK STATION O o o MAKEUP STORAGE UMT TANK PAB g i a ga s_ e s :=- -@ [-si. ) l = l T sanno i 4 I i EN Ewen. sysuu I I a cosman g i I O g l l j_ e l 1I = G = l i _ 1 , -e- = ~ =- ;) t . l i i I I 4 i GE > " " ' ' e _v.r ,.=- e--- 8EI M NCyc.am,1 a.D K _~ ~_ L " =, NMW WNME wafer ST37tM -_T_ -- B.6-2 ODCM Rev. 17 el i l ~ _-_ __ ___J FIGURE B.6-2 GASEOUS EFFLUENT STREAMS. RADIATION MONTTORS. AND BADWASTE TREATMENT SYSTEM AT SEABROOK STATION CONTAINMENT Ei"n, ' IDunmo Mocesso "00f 0"'Y8 ButLDING O -, S Tuntest _ - ttt _cyyy ya . I# AEACFtNt N g q S CONDARY VACU,UM puu s ? ) )/ ' GH3= ; Y , j CONTAseMENT PURGE AS -g ]_ l es SLOWOOWN Ft. ASH TANK my SASEQUS WASTE PROCESSES 4 SYSTEM ,,. = cat %= o ,. ven m= - l euAfC SED ,, (" * ._ i i oman - ,= i CHAACCAL ESS < = l ~ t CC^- e I i ?=2" - h 5 [h wm, = .]5 1 -' 7 @ qj v Sun.osso l i, AUMEAMIVSUtaget WWifAst = 1808 9 Y L M.tEPAfL15L L , C CMARCOALFLTER mM.nAouvan mowron \ B.6-3 ODCM Rev. 16 7.0 RASES FOR DOSE CALCUIATION METHODS 7.1 LIQUID RELEASE DOSE CALCUIATIONS This section serves: (1) to document the development and conservative nature of Method I equations to provide background inforniation to Method I users, and (2) to identi yf the general equations, parameters and approaches to Method II-type dose I assessments. Appendix C provides the bases for the EMS software which is used to implement the dose and dese rate calculations indicated as Method IA. Method I may be used to show that the Technical Specifications which limit off-site total body dose from liquids (3.11.1.2 and 3.11.1.3) have been met for releases over the appropriate periods. The quarterly and annual dose limits in Technical Specification 3.11.1.2 are based on the AIARA design objectives in 10CFR50, Appendix I Subsection II A. The minimum dosa values noted in Technical Specification 3.11.1.3 are " appropriate fractions," as determined by the NRC, of the design objective to ensure that radwaste equipment is used as required to keep off-site doses AIARA. Method I was developed such that "the actual exposure of an individual . . . is unlikoly to be substantially underestimated" (10CFR50, Appendix I) . The definition, below, of a single " critical receptor" (a hypothetical or real individual whose behavior results in a maximum potential dose) provid2s part of the conservative margin t;o the calculation of total body dose in Me'. nod I. Method II allows that actual individuals, associated with identifiabla exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis for a critical receptor assuming all principal pathways present instead of any real individual. That analysis was called the " base case;" it was then reduced to form Method I. The general equations used in the base case analysis are also used as the starting point in Method II evaluations. The base case, the method of reduction, O and the assumptions and data used are presented below. The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor [in the form of dose factors DF1m (area /pC1)] for a unit activity release of each radioisotope in liquid effluents was derived. The base case analysis uses the general equations, methods, data and assumptions in Regulatory Guide 1.109 (Equations A-3 and A-7, Reference A). The liquid pathways contributing to an individual dose are due to consumption of fish and invertebrates, shoreline activities, and swimming and boating near the discharge point. A normal operatin5 Pl ant discharge flow rate of 918 ft 8/see was used with a mixing ratio of 0.10. The mixing ratio of 0.10 corresponds to the minimum expected prompt dilution or near-field mixing zone created at the ocean surface directly above the multiport diffusers. (Credit for additional dilution to the outer edge of the prompt mixing zone which corresponds to the l'F surface isotherm (mixing ratio .025) can be applied in the Method II calculation for shoreline exposures only since the edge of this isotherm typically does not reach the shoreline receptor points during the tidal cycle. The mixing ratio for aquatic food pathways in Method II assessments shall be limited to the -same value (0.10) as applied in Method I for near-field mixing, or prompt dilution only. l O B 7-1 ODCM Rev. 16 7.1 LIQUID RELEASE DOSE CALCULATIONS (C:ntinu d) The requirements for the determination of radiological impacts resulting from releases in liquid effluents is derived froni 10CFR50, Appendix I.Section III.A.2 of Appendix I indicates that in making the assessment of doses to hypothetical receptors, "The Applicant may take account of any real phenomenon or factors cetually affecting the estimate of radiation exposure, including the characteristics of the plant, modes of discharge of radioactive materials, physical processes tending to attenuate the quantity of radioactive material to which an individual would be exposed, and the effects of averaging exposures over time during which determining factors may fluctuate." In accessing the liquid exposure pathways that ; characterize Seabrook Station, the design and physical location of the Circulating Water Discharge System needs to be considered within the scope of Appendix I. Seabrook utilizes an offshore submerged multiport diffuser discharger for rapid dissipation and mixing of thermal effluents in the ocean environ *ent. The 22-port diffuser section of the Discharge System is located in approxintely 50 to 60 feet of water with each nozzle 7 to 10 feet above the sea floor. Water is i discharged in a generally eastward direction away from the shoreline through the l multiport diffuser, beginning at a location over one mile due east of Hampton Harbor inlet. This arrangement effectively prevents the discharge plume (at least to the 1 ! degree or 40 to 1 dilution isopleth) from impacting the shoreline over the tidal j cycle. l Eleven riser shafts with two diffuser nozzles each form the diffuser and are spaced about 100 feet apart over a distance of about 1,000 feet. The diffusers are designed to maiatain a high exit velocity of about 7.5 feet per second during power operations. Each nozzle is angled approximately 20 degrees up from the horizontal plane to preva.nt bottom scour. These high velocity jets passively entrain about ten volumes of fresh ocean water into the near field jet mixing region before the plume reaches the water surface. This factor of 10 mixing occurs in a very narrow zone of less than 300 feet from the diffuser by the time the thermally buoyant plume reaches the ocean surface. This high rate of dilution occurs within about 70 seconds of discharge from the diffuser nozzles. The design of the multiport diffuser to achieve a 10 to 1 dilution in the near field jet plume, and a 40 to 1 dilution in the near mixing zone associated with the 1 degree isotherm, has been verified by physical model tests (reference " Hydrothermal Studies of Bifurcated Diffuser Nozzles and Thermal Backwashing - Seabrook Station," Alden Research Laboratories, July 1977) . During shutdown periods, when the plant only requires service water cooling flow, the high velocity jet mixing created by the normal circulating water flow at the diffuser nozzles is reduced. However, mixing within the discharge tunnel water volume is significantly increased (factor of about 5) due to the long transit time (approximately 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months ) for batch waste discharged from the plant to travel the three miles through the 19-foot diameter tunnels to the diffuser nozzles. Additional mixing of the thermally buoyant effluent in the near field mixing zone assures that an equivalent overall 10 to 1 dilution occurs by the time the plume reaches the ocean surface. O B.7-2 ODCM Rev. 16 l 7.1 LIQUID RELEASE DOSE CALCULATIONS (C:ntinusd) The dose assessment models utilized in the ODCM are taken from NRC Regulatory (

Guide 1.109. The liquid pathway equations include a parameter (M,) to account for

\ the mixing ratio (reciprocal of the dilution factor) of effluents in the environment at the point of exposure. Table 1, in Regulatory Guide 1.109, defines the point of exposure to be the location that is anticipated to be occupied during plant lifetime, or have potential land and water usage and food pathways as could actually exist during the term of plant operation. For Seabrook, the potable water and land irrigation pathways do not exist since saltwater is used as the receiving water body for the circulating water discharge. The three pathways that have been factored into the assessment models are shoreline exposures, ingestion of invertebrates, and fish ingestion. With respect to shoreline exposures, both the mixing ratios of 0.1 and 0.025 are extremely conservative since the effluent plume which is discharged over one mile offshore never reaches the beach where this type of exposure could occur. Similarly, bottom dwelling invertebrates, either taken from mud flats near the shoreline or from the area of diffuser, are not exposed to the undiluted effluent plume. The shore area is beyond the reach of the surface plume of the discharge, and the design of the upward directed discharge nozzles along with the thermal buoyancy of the effluent, force the plume to quickly rise to the surface without affecting bottom organisms. Consequentially, the only assumed exposure pathway which might be impacted by the near field plume of the circulating water disch rge is finfish. However, the mixing ratio of 0.1 is very conse c.rative because fish will avoid both the high exit velocity provided by the dischmece nozzles and the high thermal temperature difference between the water discharged from the diffuser and the ambient water () ( ,/ temperature in the near field. In addition, the dilution factor of 10 is achieved within 70 seconds of discharge and confined to a very small area, thus prohibiting any significant quantity of fish from reaching equilibrium conditions with radioactivity concentrations created in the water environment. The mixing ratio of 0.025, which corresponds to the 1 degree thermal near field mixing zone, is a more realistic assessment of the dilution to which finfish might be exposed. However, even this dilution credit is conservative since it neglects the plant's operationsl design which discharges radioactivity by batch mode. Batch discharges are on the order of only a few hours in duration several times per week and, thus, the maximum discharge concentrations are not maintained in the environment long enough to allow fish to reach equilibrium uptake concentrations as assumed in the dose assessment modeling. Not withstanding the above expected dilution credit afforded at the 1 degree isotherm, all Method II aquatic food pathway dose calculations shall conservatively assume credit for prompt dilution only with an M, - 0.10. When dose impacts from the fish and invertebrate pathways are then added to the conservative dose impacts derived for shoreline exposures, the total calculated dose is very unlikely to have underestimated the exposure to any real individual. The recommended value for dilution of 1.0 given in NUREG-0133 is a simplistic l assumpoien prsvi6ed so that a single model could be used with any plant design and I physical discharge arrangement. For plants that utilize a surface canal-type discharge structure where little entrainment mixing in the environment occurs, a dilution factor of 1.0 is a reasonable assumption. However, in keeping with the guidance provided in Appendix I to 10CFR50, Seabrook has determine site-specific mixing ratios which factor in its plant design. . V(} B.7-3 ODCM Rev. 16 7.1 LIQUID RELEASE DOSE CALCULATIONS (C:ntinaed) The transit time used for the aquatic food pathway was 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and for choreline activity 0.0 hours0 days 0 hours 0 weeks 0 months . Table B.7-1 outlines the human consumption and use factors used in the analysis. The resulting, site-specific, total body dose factors j cppear in Table B.1-11. Appendix A provides an example of the development of a Method I liquid dose conversion factor for site-specific conditions at Seabrook. 7.1.1 Dose to thg._Tpfal Body For any liquid release, during any period, the increment in total body dose l l from radionuclide "i" is: l ADeb = k Qi DFL,,3 i (mrem)()(#Ci) pCi (7-1) where: DFLi a - Site-specific total body dose factor (mrem /pCi) for a liquid release. It is the highest of the four age groups. See Table B.1-11. Qi - Total activity (pci) released for radionuclide "i". K - 918/Fa (dimensionless); where Fe is the average dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3 /sec). Method I is more conservative than Method II in the region of the Technical Specification limits because the dose factors DFL u used in Method I were chosen i for the base case to be the highest of the four age groups (adult, teen, child and infant) for that radionuclide. In effect each radionuclide is conservatively represented by its own critical age group. 7.1.2 Dose to the Critical Orean The mechods to calculate maximum organ dose parallel to the total body dose l l methods (see Section 7.1.1). f I l l O1 B.7-4 ODCM Rev. 16 l l 7.1 LIQUID RELEASE DOSE CALCUIATIONS (Ccntinuid) 7.1.2 Dose to the Critical Orzan (Continued) For each radionuclide, a dose factor (aren/pci) was determined for each of seven organs and four age groups. The largest of these was chosen to be the maximum organ dose factor (DFL 3 .) for that radionuclide. DFLw also includes the external dose contribution to the critical organ. For any liquid release, during any period, the increment in dose from radionuclide "i" to the maximum organ is: AD, = k Qi DFL,, (7-2) (mrem) () (pCi) pCi where: DFL$ . - Site-specific maximum organ dose factor (mrem /pci) for a liquid release. See Table B.1-11. Q3 - Total activity (pCi) released for radionuclide "i". K - 918/Fa (dimensionless); where F4 is the average dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 8/sec). NJ O v B.7-5 ODCM Rev. 16 _ 6 - ", 1 _ y . . r t v O _

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7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.1 Total Body Dose Rate From Noble Casca This section serves: (1) to document the development of the Method I l equation, (2) to provide background information to Method I users, and (3) to identify the general equations, parametern and approaches to Method II-type dose rate assessments. Method I may be used to show that the Technical Specification which limits total body dose rate from noble gases released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak noble gas release rate. Method I was derived from general equation B E in Regulatory Guide 1.109 as follows: 6 - 1E46 [X/Q]Y Qi DFB, (7-3) 'eren' , 'pCi' sec ' sci ' arem e3 yr pCi m3 sec pci-yr O , , , where: [X/Q)? - Maximum off-site receptor location long-term average gamma atmospheric dispersion factor. i Qi - Release rate to the environment of noble gas "i" (pCi/sec). 3 DFB 3 - Gamma total body dose factor, arem-5 . See Table B.1-10. pCi-yr (Regulatory Guide 1.109, Table B-1). l Elevated and ground level gaseous effluent release points are addressed separately through the use of specific [X/Q]v. For an elevated gaseous effluent release point and off-site receptor, Equation 7-3 takes the form: O G B.7-7 ODCM Rev. 16 7.2 CASEOUS RELEASE DOSE CAlfULATIONS 7.2.1 Total Body Dose Rate From Noble Cases (Continued) O 6tbc.) = (1E+06) * (8.5E-07) + i{ (Q, + DFBi ) 3 ' mrem' 'pC1' _sec pCi . mrem-m yr = pCi m 3 .{ sec pCi-yr . which reduces to: (3-3a) 6 tbc.) = 0.85 . { (Q +i DFB i ) i 3 ' mrem' , pCi-sec 'pC i ' , mrem-m yr C1-m 3 sec pCi-yr For a ground level gaseous effluent release point and o. '-site receptor, Equation 7-3 takes the form: 6tbce) = (1E+06) + (3.4E-06) +I { (Qi + DFBi ) which reduces to: tb<s) = 3.4 + { (Q ie DFB i ) i ' 3 (3-3b) ' mrem' , pCi-sec 'pC i ' , mrem-m yr pCi-e3 , sec , , pCi-yr The selection of critical receptor, outlined in Section 7.3 is inherent in the derived Method I, since the maximum expected off-site long-term average atmospheric dispersion factor is used. The sum of doses from both plant vent stack and ground level releases must be considered for determination of Technical Specification compliance. All noble gases in Table B.1-10 should be considered. O B.7-8 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.1 Total Body Dose Rate From Noble Cases (Continued) , \ A Method II analysis could include the use of actual concurrent meteorology to l assess the dose rates as the result of a specific relaase. 7.2.2 Skin Dose Rate From Noble Cases This section serves: (1) to document the development of the Method I equation, (2) to provide background information to Method I users, and (3) to identify the general equations parameters and approaches to Method II-type dose rate f assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Only the differences are presented here. Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak noble gas rnlease rate. The annual skin dose limit is 3,000 arem (from NBS Handbook 69, Reference D, pages 5 and 6, is 30 rem /10). The factor of 10 reduction is to account for nonoccupational dose limits. It is the skin dose commitment to the critical, or most limiting, off-site receptor assuming long-term site average meteorology and that the release rate reading remains constant over the entire year. Method I was derived from the general equation B-9 in Regulatory Guide 1.109 as follows: O D' = 1.11 DL,. + 3.17E44 Qi (X/Q) DFS, (7-4) l 3 ' mrem' , ' mrem' ' mrad' 'pCi-yr' Ci sec mrem-m yr mrad , yr Ci-sec yr m3 ' , PC i -yr , where: 1.11 - Average ratio of tissue to air absorption coefficients (will convert mrad in air to area in tissue). DFSg - Beta skin dose factor for a semi-infinite cloud of radionuclide "i" which includes the attenuation by the outer " dead" layer of the skin. 9 B.7-9 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CAlfUIATIONS 7.2.2 Skin Dose Rate From Noble Cases (Continued) D!,, = 3.17E44 [ Q, [X/Q) DF Y i (7-5) i P , 3 ' mrad' 'pCi -yr' mrad-ci = (Ci)yr ( sec) pCi-yr yr Ci-sec m3 DFJ - camma air dose factor for a uniform semi-infinite cloud of radionuclide "i". Now it is assumed for the definition of (X/QT) from Reference 8 that: Dlinit, - D!,,. [X/Q]Y/[X/Q) (7 6) ' mrad' ' mrad' sec m3 yr yr m3 sec cnd Q, - 31.54 Q, 'Ci ' 'Ci -sec' 'gCi' ,yr . . pCi-yr . . sec co: 7 (7-8) 6.11. - 1.11 1E+06 (X/Q)1 Qi

DF i

,pCi mrem mrem pCi sec mrad-m3, , yr , ,mr ad, M, ,7 ,s e c, ,pci-yr, +1E+06 X/Q Qi DFS i ,pCi 3, pCi sec mrem-m %, ,7, ,8ec, ,PCi-yr, O B.7-10 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCULATIONS 7.2.2 Skin Dose Rate From Noble Gases (Continued) Substituting atmospheric dispersion factors for an elevated gaseous effluent release point, Equation 7-8 takes the following form: 6a3<,3 = [1.11 + 1E+06

8. 5E-07 * (Q3

DFI)) + [lE+06

8.2E-07 * (Q1

DFSi )]

which yields: beac,3 = [0.94 { (Qi

DFj)) + [0.82 { (Qi

DFS3 )) (7-9a)

a

'aren' , 'pci-sec-arem' g 'pci , mrem m 8' + pCi-see p "pCi , mrem-m 3' , yr , , pCi-m3 -arad , ,s e c pCi-yr, pCi-m 3 ,s e c pGi-yr, defining: DF[g,3 = 0.94 DFI + 0.82 DFS i (7-10a) Then the off-site skin dose rate equation for an elevated gaseous effluent release point is: O Deat.) = ['Qi

DF[c.3 (3-4a) mrem

,g pCi , mrem-see , yr , ,s e c pci-yr , For an off-site receptor and a ground level gaseous effluent release point, Equation 7-8 becomes: 6 g3<,3 = [1.11*lE+06 *3.4E-06 *{ (Q i+DFi)] + [1E+06 *l.0E-05 *{ (Q ioDFS3 )] which yields: batog,3 = [3.8 { (Q1

DFl)] + [10 { (Q

DFS )] i 3 (7-9b)

= { Q3 [3.8 DFZ + 10 DFSi ] O B.7-11 ODCM Rev. 16 7.2 CASEOUS RELEASE DOSE CALCUIATIONS 7.2.2 Skin Dose Rate From Noble Gases (Continued) defining: DF[g,3 = 3.8 DF] + 10 DFSt (7-10b) Then the off-site skin dose rate equation for ground level gaseous effluent release points is: (3-4b) D kin (s) "i E Qi

DF[< 3 The selection of critical receptor, outlined in Section 7.3, is inherent in the derived Method I, as it is based on the determined maximum expected off-site ctmospheric dispersion factors. All noble gases in Table B.1-10 must be considered.

7.2.3 Critical Orran Dose Rate From Iodines. Tritium and Particulates With Half-Lives creater Than Eight Days This section serves: (1) to document the development of the Method I equa' tion, (2) to provide background information to Msthod I users, and (3) to identify the general equation's parameters and approached to Method II type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Method I may be used to show that the Technical Specification which limits organ dose rate from iodines, tritium and radionuclides in particulate form with half lives greater than 8 days released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak above-mentioned release rates. The annual organ dose limit is 1500 mrem (from NBS Handbook 69, Reference D, pages 5 and 6). It is svaluated by looking at the critical organ dose commitment to the most limiting off-site receptor assuming long-term site average meteorology. The equation for be , is derived from a form of Equation 3-8 in Section 3.9 by cpplying the conversion factor, 3.154E+07 (sec/yr) and converting Q to Q in pCi/see: O B.7-12 ODCM Rev. 16 l ( 7.2 GASEOUS RELEASE DOSE CALCULATIONS 1 7.2.3 Critical Orean Dose Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) D,, = 3.15E+07 * { (Q

DFG .) i i (7-12)

, , , , , 1, , , l sec pCi mrem mrem , yr , ,yr, p ,s e c, ~TT, p f { Equation 7-12 is rewritten in the form: D,,= { (Qi

DFG',,) (7-12a) i i

aren pCi mrem-se'c ,, p , , yr , ,sec , pGi-yr , where: DFG[,, = 3.154E+07

DFGi ., (743) arem-sec sec mrem

,K pci-yr , ,yr, The dose conversion factor, DFGi .., has been developed for both elevated '# gaseous effluent release points and 5round level gaseous effluent release points (DFG.<,) and DFG i t .c,3), respectively. These dose factors are used to determine accumulated doses over extended periods and have been calculated with the Shielding Factor (SF) for ground plane exposure set equal to 0.7, as referenced in Regulatory Guide 1.109. In the case of the dose rate conversion factors (DFG' to.c.) and DFG'i.,<,3), the dose conversion factors from which they were derived were calculated with the Shielding Factor (SF) for ground plane exposure set equal to 1.0. For an off-site receptor and elevated effluent release point, the critical organ dose rate equation is: D,.c 3 = { (Q3

DFG's, <,3) (3-Sa) i ,

mrem ,, p pCi , mrem-sec , yr , ,s e e pCi-yr , For an off-site receptor and ground level effluent release point, the critical organ dose rate equation is: N t J B.7-13 ODCM Rev. 16 l 1 7.2 GASEOUS RELEASE DOSE CALCULATIONS 7.2.3 Critical Orzan Dose Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Eicht Days (Continued) D cots) " b (91

DFG' i.,g,3) MM 2 , ,

mrem ,p pCi , mrem-sec yr , ,s ec pGi-yr , l The selection of critical receptor, outled in Section 7.3 is inherent in l Method I, as are the expected atmospheric dispersion factors. In accordance with the Basis Statement 3/4.11.2.1 in NUREG-0472, and the base's section for the organ dose rate limit given for Technical Specification 3.11.2.1, a Method II dose rate calculation, for compliance purposes, can be based on restricting the inhalation pathway to a child's thyroid to less than or equal to 1,500 mrem /yr. Concurrent meteorology with time of release may also be used to cssess compliance for a Method II calculation. 7.2.4 Gamma Dose to Air From Noble Gases This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose essessments . Method I may be used to show that the Technical Specification 3.11.2.2 which limits off-site gamma air dose from gaseous effluents has been met for releases over appropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated gamma air dose in eff-site unrestricted areas. NUREG/CR-2919 presents a methodology for determining atmospheric dispersion factors (CHI /Q values) for intermittent releases at user specified receptor locations (intermittent releases being defined as releases with durations between 1 and 8,760 hours0.0088 days 0.211 hours 0.00126 weeks 2.8918e-4 months ). The CHI /Q values for intermittent releases are determined by linearly interpolating (on a log-log basis) between an hourly 15-percentile CHI /Q value and an annual average CHI /Q value as a function of release duration. This rethodology has been adopted to produce a set of time-dependent atmospheric dispersion factors for Method I calculations. For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption that D'gi,ts. - D1 [X/Q)1/[X/Q): O B.7-14 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.4 C-'- = Dome to Air From Noble Cases ADIir - 3.17E+4 (X/Q]? Qi DFl (7 14) (arad) - PC i-yr' 'see' (C1) 'arad-m'8 ci-sec, [ ,pGi-yr where: Number of pCi per Ci divided by the number of seconds per 3.17E+04 - year. [X/Q]7 - Annual average gamma atmospheric dispersion factor for the receptor location of interest. Qi - Number of curies of noble gas "i" released. DF's - Gamsc. air dose factor for a uniform semi-infinite cloud of radionuclide "i". O Incorporating a unitiess release duration adjustment term t-* (where "a" is a constant and "t" is the total release duration in hours), and the conversion factor for Ci to pCi (to accommodate the use of a release rate Q in pCi), and substituting the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months gamma atmospheric dispersion factor in place of the annual average gamma atmospheric dispersion factor in Equation 714 leads to: (3-6) DL - 3.17E-02 * [X/Q)b

t** * (Q4

DFI) 3, pCi-yr sec arad-m (arad) -

,Gi-sec, p

{ pCi e pGi-yr For an elevated release, the equation used for an off-site receptor is:

D {q, . pp air (e) - 3.17E-02 * [1.0E-05]

t-o.275 O

B.7-15 ODCM Rev. 16 l 7.2 CASEOUS RELEASE DOSE CALCULATIONS i 7.2.4 G=== Dose to Air From Noble Cases l which leads to: ( M a) D!i,(.3 - 3.2E-07

t-o.27s . p {g, . pp7}

Ci-yr' 3 (mrad) . P 3 Ci-m ,

{ aCi

mrad-m' C

P i-yr, For a ground-level release, the equation used for an off-site receptor is: Dair qt . pp (g) - 3.17E-02 * [4.9E-05)

t-o.2s3 which leads to:

D!i,c,3 - 1.6E-06

t-o.2ss . { {q , pp7)

A 'PCi-yr' "#"d~" (mrad) - 3 ,yCi-m ,

{ uCi

pCi-yr, The major difference between Method I and Method II is that Method II would u:e actual or concurrent meteorology with a specific noble. gas release spectrum to determine (X/Q]1 rather than use the site's long-term average meteorological dispersion values.

7.2.5 Beta Dose to Air From Noble Gases I This section serves: (1) to document the development and conservative nature of Method I equations to provide back5round information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose casessments. Method I may be used to show that Technical Specification 3.11.2.2, which limits off-site beta air dose from gaseous effluents, has been met for releases over cppropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated beta air dose in off-site unrestricted area locations. For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109: l O B 7-16 ODCM Rev. 16 f 1 7.2 CASEOUS RELEASE DOSE CALCUIATIONS 7.2.5 Beta Dose to Air From Noble Cases (Continued) AD{i, - 3.17E-02 X/Q Qi DF{ (7-15) mrad-m3, PCi-yr sec (arad) . (pCi) ,pci-yr, ,ci-sec, p 7, where: I DF# 1 - Beta air dose factors for a uniform semi-infinite cloud of radionuclide "i". Incorporating the term t-* into Equation 7-15 leads to: l I D{i, - 3.17E-02

X/Q

t-*

{L (Qi

Dd) (3-7) pCi-yr sec *d-"

l (arad) - ,ci-sec, p 7 *()*{ pCi * "Ci-yr p , Where X/Q - average 1-hour undepleted atmospheric dispersion factor. For an elevated release, the equation used for an off-site receptor is: e D{1,c 3 - 3.17E-02 e 1.3E-05

t-0 3 * { (Qi

Dd)

( i PCi-yr sec aradd, (mrad) . ,ci-sec, p ,7 ()*{ pCi e pCi-yr, 1 which leads to: 1 D{1,c.3 - 4.1E-07

t 3 * [ (Qi

DF{} (3-7a)

l Ci-yr' pCi e arad-m' 3

(mrad) . P ,pci-m3,

()*{ ,

P Ci yr, For a ground-level release, the equation used for an off-site receptor is: l l l O B.7-17 ODCM Rev. 16 7.2 CASEOUS RELEASE DOSE CALCULATIONS 7.2.5 Beta Dose to Air From Noble Cases (Continued) O D{1,g,3 - 3.17E-02

1.9E-04

t-0 318 * { (Qi

DF()

i P Ci-yr ' Ci e arad-m' 3 (mrad) - p ,ci-sec, , [sec'* ( ) * , pGi-yr, which leads to: D{1,c,3 - 6.OE-06

t-0 318 * { (Qi

DFT)

'PCi-yr' Ci

mrad-m' 3

(mrad) - ,yCi-m 3,

()*{ PGi-yr, 7.2.6 Dose to Critical Orean From Iodines. Tritium and Particulates With Half-Lives Greater Than Eight Days This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose essessments.

Method I may be used to show that the Technical Specifications which limit off-site organ dose from gases (3.11.2.3 and 3.11.4) have been met for releases over the appropriate periods. Technical Specification 3.11.2.3 is based on the ALARA cbjectives in 10CFR5% Appendix I, Subsection II C. Technical Specification 3.11.4 is based on Envirce ., cal Standards for Uranium Fuel Cycle in 40CFR190, which cpplies to direct radiation as well as liquid and gaseous effluents. These methods cpply only to iodine, tritium, and particulates in gasecar effluent contribution. Method I was developed such that "the actual exposure of an individual . . . is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use below of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis of a critical receptor assuming all rathways present. That analysis was called the " base case"; it was then reduced to ' tm Method I. The base case, the method of reduction, and the assumptions and data used are presented below. O B.7 18 ODCM Rev. 16 2 r - 7.2 GASEOUS RELEASE DOSE CALCU1ATIONS 7.2.6 Dose to critical Orean From Iodines. Tritium and Particulates With Half-1.ives Greater Than Einht Days The steps performed in the Method I derivation follow. First, the dose impact to the :ritical receptor [in the form of dose factors DFG ., (arem/pCi)] for a unit i activity release of each iodine, tritium, and particulate radionuclide with half lives g,reater than eight days to gaseous effluents was derived. Six exposure pathws /s (ground plane, inhalation, stored vegetables, leafy vegetables, milk, and meat in5estion) were assumed to exist at the site boundary (not over water or marsh l areas) which exhibited the highest long-term X/Q. Doses were then calculated to six ! organs (bone, liver, kidney, lung, CI-LLI, and thyroid), as well as for the whole body and skin for four age groups (adult, teenager, child, and infant) due to the seven combined exposure pathways. For each radionuclide, the highest dose per unit activity release for any organ (or whole body) and age group w'as then selected to become the Method I site specific dose factors. The base case, or Method I l analysis, uses the general equations methods, data, and assumptions in Regulatory Guide 1.109 (Equation C-2 for doses resulting from direct exposure to. contaminated 5round plane; Equation C-4 for doses associated with inhalation of all radionuclides to different organs of individuals of different age groups; and Equation C-13 for

doses to organs of individuals in different age groups resulting from ingestion of I radionuclides in produce, milk, meat, and leafy vegetables in Reference A). Tables

! B.7-2 and B.7-3 outline human consumption and environmental parameters used in the analysis. It is conservatively assumed that the critical receptor lives at the ! " maximum off-site atmospheric dispersion factor location" as defined in Section 7.3. The resulting site specific dose factors are for the maximum organ which combine the limiting age group with the highest dose factor for any organ with each nuclide. These critical organ, critical age dose factors are given in Table B.1-12. l Appendix A provides an example of the development of Method I gaseous dose conversion factor for site-specific conditions at Seabrook. For any iodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "i= is: AD.. i - Q1DFG . i (7-16)

l. where DFG . is the critical dose factor for radionuclide "i" and Q3 is the activity i

of radionuclide "i" released in microcuries. l Applying this information, it follows that the general form for the critical organ dose equation is: i O B.7-19 ODCM Rev. 16 ] [ 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.6 Dose to Critical Orman From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) D., - (X/Q)$*g}/(X/Q)df

t-* * (Q1

DFG3 ,,) (3-8) mrem'

'sec' sec' aren 7,7 / * () * { uCi

7 l Substituting specific values associated with the maximum off-site receptor location and elevated release condition yields:

l D .c.3 - (1.12E-05)/(7.55E-07)

t-o.2s7 * (Qi

DFG i .(.3) which reduces to:

D, <,3 - 14. 8

t-o.zs7 *

(Qi

DFGi .c.3) (3-8a)

For the maximum off-site receptor location and ground-level release conditions, the equation is: l 1 D <,3 - (1.71E-04)/(9.64E-06)

t-0 318 * (Qi

DFG3 ,,c,3) which reduces to:

D, g,3 - 17. 7

t-o.sts * (Q

DFG ) (3-8b) 7.2.7 Soecial Recentor Caseous Release Dose Calculations Technical Specification 6.8.1.4 requires that the doses to individuals involvad in recreational activities within the site boundary are to be determined cnd r.1 ported in the Annual Radioactive Effluent Release Report.

The gaseous dose calculations for the special receptors parallel the bases of the gaseous dose rates and doses in Sections 7.2.1 through 7.2.5. Only the differences are presented here. The special receptor XQs are given in Table B.7-5. 7.2.7.1 Total Body Dose Rate From Noble Cass_g Method I was derived from Regulatory Guide 1.109 as follows: 1 O B.7-20 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.1 Total Body Dose Rate From Noble Gases (Continued) ba - 1E+06 [X/Q]1 {' Qi DFB i (7-3) 1 General Equation (7-3) is then multiplied by an Occupancy Factor (OF) to account for the time an individual will be at the on-site receptor locations during the year. There are two special receptor locations on-site. The " Rocks" is a boat landing area which provides access to Browns River and Hampton Harbor. The Seabrook Station UFSAR, Chapter 2.1, indicates little boating activity in either Browns River or nearby Hunts Island Creek has been observed upon which to determine maximum or conservative usage factors for this on-site shoreline location. As a result, a default value for shoreline activity as provided in Regulatory Guide 1.109, Table E-5, for maximum individuals was utilized for determining the " Rocks" occupancy factor. The 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months / year corresponds to the usage factor for a teenager involved in shoreline recreation. This is the highest usage factor of all four age groups listed in Regulatory Guide 1.109, and has been used in the ODCM to reflect the maximum usage level irrespective of age. Regulatory Guide 1.109 does not provide a maximum individual usage factor for activities similar to those which would be associated with the Seabrook Station Science & Nature Center. Therefore, the usage factor used in the ODCM for the Science & Nature Center reflects the observed usage patterns of visitors to the facility. Individuals in the public who walk in to look at the saxhibits on display and pick up available information stay approximately 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months each. Tour groups who schedule visits to the facility stay approximately 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . For conservatism, it was assumed that an individual in a tour group would return five times in a year, and stay 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months on cach visit. These assumptions, when multiplied together, provide the occupancy factor of 12.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months / year used in the ODCM for public , activities associated with the Science & Nature Center. i For the Science & Nature Center, and the " Rocks", the occupancy factors (OFs) are: Science & Nature Center - 12.5 hrs /yr '"- 0.0014 5760 hrs /yr The " Rocks" - 67 hrs /yrtu - 0.0076 5760 hrs /yr I l 1 (D Taken from Seabrook Station Technical Specifications (Figure 5.1-1). B,7-21 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.1 Total Body Dose Rate From Noble Cases (Continued) substituting in the annual average gamma X/Qs: [X/Q)? - 1.lE-06 sec/m3 (Science & Nature Center) for primary vent stack releases. - 5.3E-06 seem3 (Science & Nature Center) for ground level releases. - 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases. - 2.6E-05 sec/m3 (The " Rocks") for ground level releases. end multiplying by: OF - 0.0014 (Science & Nature Center) ! I l - 0.0076 (The " Rocks") gives: bagg,3 = 0.0015 * { (Qi . DFB1) (arem/yr) (3-3c) bagg,3 = 0.0074 * (41

DFB1 ) (arem/yr) (3-3d) bang,3 = 0.038 * (Qi

DFB1 ) (arem/yr) (3-3e) bagg,3 = 0.2 + { (Qi

DFBi ) (mrem /yr) (3-3f)

A i where: Nest.). basts). $nat ), and 6an(s) - total body dose rates to an individual at the Science & Nature Center and the " Rocks" (recreational site), respectively, due to noble gases in an l elevated (e) and ground level (g) release, Qi and DFBi are as defined previously. 7.2.7.2 Skin Dose Rate From Noble Cases Method I was derived from Equation (7-8): 6,31, - 1.11 lE+06 [X/Q)2 { Q iDFl + (7-8) lE+06 X/Q { Qi DFS i O B.7-22 ODCM Rev. 16 i l 7.2 GASEOUS REIJASE DOSE CALCUIATIONS ; 7.2.7.2 Skin Dose Rate From Noble Gagig (Continued) N substituting in the annual average gamma X/Qs: [X/Q)T - 1.1E-06 sec/m 3 (Science & Nature Center) for primary vent stack l releases. - 5.3E-06 sec/m3 (Science & Nature Center) for ground level release points. - 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases. I - 2.6E-05 sec/m3 (The " Rocks") for ground level release points. l l and the annual average undepleted X/Qs: X/Q - 1.6E-06 sec/m 3 (Science & Nature Center) for primary vent stack releases. - 2.3E-05 sec/m3 (Science & Nature Center) for ground level release points. - 1.7E-05 sec/m3 (The " Rocks") for primary vent stack releases. - 1.6E-04 sec/m3 (The " Rocks") for ground level release points. ! and multiplying by: OF - 0.0014 (Science & Nature Center) , - 0.0076 (The " Rocks") gives: bgigc,3 = 0.0014 Qi [1.22 DFj + 1.60 DFS i ) for an elevated release point. Daigc,3 = 0.0014 Qi [5.88 DFI + 23 DFS ) for a ground level release point. t baigc,3 = 0.0076 Qi [5.55 DFl + 17.0 DFS i ] for an elevated release point. baigc,3 = 0.0076 Qi [28.9 DFl + 160 DFSi ] for a ground level release point. and the equations can be written: batsc.3 = 0.0014 * (Qi e DFhc.3) (3-4c) l B.7-23 ODCM Rev. 16 l 7.2 GASEOUS RELEASE DOSE CALCULATIONS 7.2.7.2 Skin Dose Rate From Noble Cases (Continued) Daisc,3 = 0.0014 * { (Qi

DFuts)) (3-4d)

Daisc.) = 0.0076 * { (Qi e D F ac,3) (3-4e) Daigc,3 = 0.0076 * { (Qi

DFac,3) (3 4f) where:

$skisc.3 bakinzcs). b atis c .) , and 641gc,3 - the skin dose rate (mrem /yr) to an individual at the Science & Nature Center and the " Rocks", respectively, due to noble gases in an elevated (e) and ground level (g) release, Qi - defined previously, and DIrc.3, i DIzcs), Diag.3and t t DIac,3 - the combined skin dose factors for radionuclide "i" for the Science & Nature Center and the " Rocks", respectively, for elevated (e) and ground level (g) release points (see Table B.1-13). 7.2.7.3 Critical Organ Dose Rate From Iodines. Tritium and Particulates With Half-Lives Creater Than Eieht Days The equations for 6.. are derived in the same manner as in Section 7.2.2, except that the occupancy factors are also included. Therefore: Deac.) = 0.0014

i{ (Qi

DFGl.ac.3) for an elevated release. (3-Sc)

D,gc,3 = 0.0014 * { (Qi

DFGleac,3) for a ground level release. (3-5d) i D,gc.) = 0.0076 * (Qi

DFGl.gc 3) for an elevated release. (3-Se)

O B.7-24 ODCM Rev. 16 7.2 GASEOUS REl. EASE DOSE CALCUIATIONS 7.2.7.3 Critical Organ Dose Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Eight Days (Continued) l beca(s) = 0.0076 * { (Q

DFG[,gg,3) for a ground level release.

i (3-5f) i where: the critical organ dose rates Neorce). beor(s). b ed(*>, and 6ean(s) - (mres/yr) to an individual at the l Science & Nature Center and the " Rocks", respectively, due to iodine, tritium, and particulates in elevated j (e) and ground level (g) releases, ( Qi - as defined previously, and DFC[,,gc.3, DFG[,ogg,3, DFG[,ac.3, and DFG[eac.3 - the critical organ dose rate factors for radionuclide "1" for the Science & Nature Center and the " Rocks", respectively, for elevated (e) and ground level (g) release points (see Tables B.1-14 and B.1-15). 7.2.7.4 G=== Dose to Air From Noble Cases Method I was derived from Equation (3-6): Dji, - 3.17E-02 * (X/Q]6

t~" * { (Qi

DF]) (3 6) i where all terms of the equation are as defined previously.

Incorporating the specific 0F and the atmospheric dispersion factor, the gamma air dose equation for the Science & Nature Center for elevated releases: DIsrt(*) - 3.17E-02

1.lE-05 t-o.252

0.0014 * { (Qi

DFI) which reduces to:

l O B.7-25 ODCM Rev. 16 7.2 CASEOUS REIIASE DOSE CALCU1ATIONS 7.2.7.4 C=== Dose to Air From Noble Cases (Continued) Dli,gg.) = 4. 9E-10

t-o.252 * (Qi

DFZ) (3-6c)

P Ci-yr' * ( )* 4Ci * "#8d~" (mrad) . 3 PCi-yr ,pCi-m , For ground-level releases, the gamma air dose equation for the Science & Nature Center becomes: D!i,cgg,3 - 3.17E-02 + 1.0E-04 t-o.szt , o,0014 . p (q, , pp7) which reduces to: (3-6d) Dji,gg,3 = 4.4E-09

t-o.szt * {i (Q3

DF])

'PCi-yr, *d~" (mrad) - * ( )*{ 4Ci * ""Gi-yr ,pci-m3 P Incorporating the specific OF and atmospheric dispersion factors for the ' Rocks" yields the gamma air dose equation for elevated releases: O D11,gg.3 - 3.17E-02 + 2.1E-05

t-8135

0.0076 * { (Qi

DF])

which reduces to: D] irate) = 5.1E-09

t-0 155 * (Q3

DF]) (3-6e)

'pci-yr' 3 (arad) - ,pci-m* ,

()*{ uCi

mrad-m '

PCi-yr, For ground-level releases, the gn=na air dose equation for the " Rocks" becomes: D!irag,3 - 3.17E-02

1.7E-04 t-o.2o*

0.0076 * { (Qi

DFI) i which reduces to:

l I l l l B.7-26 ODCM Rev. 16 I l 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.4 C= - = Dose to Air From Noble Cases (Continued) Ditents) = 4.1E-08 + t-o.204

1E (Qi *DFI) (3-6f)

Ci-yr' 8 (arad) - P T * ( )e uCi* arad-m' pCi-yr, ,9Ci-m , 7.2.7.5 Beta Dose to Air From Noble Cases Method I was derived as described in Section 7.2.5. The general form of the dose equation is: D{3, - 3.17E-02

X/QN*le t** * [ (Qi

Dd) (3-7) i i 1

l where all terms in the equation are as defined in Section 7.2.5. Incorporating the specific 0F and atmospheric dispersion factor for elevated releases into Equation 3-7 yields the following beta dose equation for the Science & Nature Center: D{1,gc.3 - 3.17E-02

4.0E-05

t-0 85

0.0014 * { (Qi

DF{}

t which reduces to:

\ D{i,st 3 - 1.8E-09

t*0 85

E (Qi

Dd) (3-7c) 1 3,

1 (mrad) . P C i-yr ,pci-m',

( )*[ uCi

mrad-m PCi-yr, For ground-level releases, the beta air dose equation for the Science & Nature Center becomes:

D(3,gg,3 - 3.17E-02

5.5E-04

t-0 8'7

0.0014 * { (Qi

DFf) i 1

l which reduces to: l l l l 1 O B.7-27 ODCM Rev. 16 l 7.2 GASEOUS RELEASE DOSE CAIEJIATIONS 7.2.7.5 Beta Dose to Air From Noble cases (Continued) D{trr(s) - 2.4E-08

t-o.s47

iE (Qi

DF{) (3-7d)

Ci-yr' i (arad) - P

( )*{ pCi

mrad-m

,pci-m 3, PCi-yr, Incorporating the specific OF and atmospheric dispersion factors for the " Rocks" yields the beta air dose equation for elevated releases: D{tra(*) - 3.17E-02

1.6E-04

t-o.24o

0.0076 *i [ (Qi

DFf) which reduces to:

Daira(*) - 3.9E-08 + t-o.24s . (q, pp{y (3 7 ) Ci-yr' * ( i (arad) - P )* Ci

mrad-m PCi yr,

,pC 1 -m' , For ground-level releases, the beta air dose equation for the " Rocks" becomes: D{i,gg,3 - 3.17E-02

1.9E-03 * ' -o.as7

0.0076 * { (Qt

DF{}

^ ! which reduces to: D{teg<g3 - 4. 6E-07

t-o.2s7 * (Q

DF{) (3-7f) 8, P Ci-yr' * ( )* uCi

mrad-m (mrad) . 3 PCi-yr,

,9Ci-m , , 7.2.7.6 Critical Orran Dose From Iodines. Tritium and Particulates With Half-Lives creater Than Eieht Days Method I was derived as described in Section 7.2.3. The Critical Organ Dose equations for receptors at the Science & Nature Center and the " Rocks" were derived from Equation 3-8. The following general equation incorporates (i) a B.7-28 ODCM Rev. 16 3 f l 7.2 GASEOUS RELEASE DOSE CALCU1ATIONS 7.2.7.6 Critical Orean Dose From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) ratio of the average 1-hour depleted atmospheric dispersion factor to the average ! annual depleted atmospheric dispersion factor, (ii) the unitless t-* term, and (iii) the OF: 1 D , - (X/Q){*d/(X/Q)l*P1

t-*

OF * { (Q

DFG3 ,,)

i 1 l see j sec (arem) - *( )*( )e uCi

I Applying the-Science & Nature Center-specific factors for elevated release conditions produces the equation:

D,,gg.) - (3.72E-05)/(1.56E-06)

t-0 8'8

0.0014 * { (Qi

DFG3 ,,c,3) which reduces to:

l Deert.) - 3.3E-02

t-0 8'8 * (Qi* DFCi,,c,3) (3-8c)

O (arem) - ( )*( )*{ gCi

For a ground-level release, the equation for a receptor at the Science & Nature Center is:

D,,sc,3 - (5.21E-04)/(2.23E-05)

t-0d'7

0.0014 * { (Qi

DFC3 , c,3) which reduces to:

D,,gg,3 - 3. 3E-02

t-0 8'7 * { (Qi

DFG 3,,c,3) (3-8d)

I (arem) - ( )*( )*{ uCi

The specific Critical Organ Dose equation for a receptor at the " Rocks" under elevated release conditions is:

O V B.7-29 ODCM Rev. 16 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.6 Critical Organ Dose From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) O Dcont.) - (1.54E-04)/(1.61E-05)

t-o.24s

0.0076 * { (Qi

DFG ,c,3) i which reduces to:

(3-8e) Dcoat.) - 7.3E-02

t-o.24s * [ 1(Qi

DFGie.c.3)

(arem) - ( )*( )*{ uCi

For a ground-level release, the equation for a receptor at the " Rocks" is:

Dcoats) - (1.80E-03)/(1.59E-04)

t-o.2s7

0.0076 * { (Qi

DFG ,,c,3)

A i which reduces to: D con (s) - 8.6E-02

t-0157 * { (Qi

DFGi ,c,3) (3-8f) 1 (arem) - ( )*( )*{ Ci

The special receptor equations can be applied under the following conditions (otherwise, justify Method I or consider Method II):

1. Normal operations (nonemergency event).

2. Applicable radionuclide releases via the station vents to the atmosphere.

If Method I cannot O B.7-30 L 6 1 d . z . . . 0 r 2 0 0 0 0 0 O M e e r u t 0 7 0 0 0 . 0 0 0 O 0 0 5 0 1 M C D O s 4 8 4 2 e . . . 0 . . . r 2 0 8 0 0 0 t 0 I G u 0 2 1 7 T s O O d . R e . . . 0 B r 2 A w e 0 T ) C o r u 7 0 0 . . 0 0 0 O 0 5 0 1 N A t 4 8 4 4 2 - E e S f 1 e a 2 0 B U R s O e e 2 S o b . 0 0 n 0 v V o 4 4 4 4 i t T ( E M A ) ) R z z g g R R R R g T N E n 0 I R < w n V N e t l i P v r d e b i r c t U 9 d s o u f t o o f D S V B F H be applied, or if the Method I dose exceeds this limit, or if a more refined calculation is required, then Method II may be applied. ODCM Rev. 16 l . . . . 0 ve o 4 8 4 4 6 5 t 2 4 1 4 1 R S 3 1 2 t 1 a 5 2 4 1 7 a 3 P 1 d , _ 6 k o 4 4 4 4 6 l t 2 1 4 1 i S 3 1 2 M 1 - 0 N a e 7 . 5 O o r . . 0 . . . . 0 8 0 0 O 6 0 1 T t 4 4 4 2 A s . 3 S P 1 K . . . 0 8 0 0 0 0 A o 4 4 4 4 6 5 E k t 2 1 4 1 S l S 3 1 2 i 1 T M _ 0 S 5 E e s 2 1 7 U c a 3 L n P 1 F e 2 F r . 0 7 f y 0 . . 0 0 4 1 OL 3 4 4 4 2 - 1 4 7 E E m l L 3 1 . 1 A a B B r AG f t e 6 T RO d g d e 0 7 F e e r 2 0 1 S r 2 4 4 R e S 3 1 1 E 1 D ) Y ) A 3 A M M ) ) ) ) D m P / / S S S S / / m L K K H H H H K g A ( ( ( ( ( ( ( ( n M i n 5 h i 0 ) 2 e e o w - ) m r r o 1 E y u u G r e " t n G n 0 . s o . i 6 v l a g . e s o P n e g o 5 R a t y s u t t e V e I i s n V - , h a u i e e e d o w d l y m m vr e e y a 0 V o n t i i e r e r f t t 1 r e T T a F a r o a n i P D e H e u t e e d 1 m e e y Y t S L m i l e i r r r l s e m e a c T u u e i f a f f l u d r a s s t a o P ) o o E H i u 8 t r r p p A n n( n n n e G l u o x x p s o o e o o o t u y u p E E i n i n O l i i r i c s u a t t u t e t e t l r i l n l p d m c ct cd cd c o o r i a i o l i a a s a r a r a s t g o r o r o n r r a r a r a r b a A S T S C H A F F P F G F G F A l ug e F P S G L I R Y P T T T T Q F F F F F H l

6 c a 1 a n n i o ) .

e u f i i ve b c t s l r d i s i a e o n e p d e . o d h s a s n r s nt l l o P M h e t e l r a o yh cF a t a m e f r o c t o ce mm n C D O O h f 0 l a r t .P o . f g a r) F 1 s e r e un t u r Pe y o o f s . r a ns a n o e a0 p h e t , n r e t c 0 o o s1 s d 2 a s e e3 - n t gt s s s a s nad e u u81 h ri e l t i wt t d e3 f o e r o n b { s . r s op t a e ? O s s e g l l g I e y h n e e t l a l a t ob r e e aP T A T f h w n g( l d sh t h s ; S o t n l n e 0 a i oi a bf ) 8 K s p r r w o 8 9 O e u e d y m1 O s l d z) e a t / R al P i mra m g) B e a g sF f e p ( t A l ni( i E e r i t r s G r o r e e n us 6 ug f r r r e t a s 5 u T y uu ud A t ) ct t i: ad A i r c s : p e o( S v a o a a o t r T i e p p s nr 9 N t y s o op l 3 E c e nns s o oi e e a u . U a1 L o( a l r ql e i e e e n i e o r d s l b mo hd V 2 E )d a r e i i wna a u e r uo r ot t t a d l l 2

7. u r f m ed a a 3 B U O n d h e od o r e e vnr -

E L B E it S A o A G C n i 0 f 6 i7 t 8 n f e unf d uo n e sii ms t o f l ei r t un i yu t o i J d 7 B O TR( e t r a c s t e i s O d a o ai sd ai mc ui F i f e rh p t r rf t h sy S f e e a o K o s p ef f s eh t sh i o t P i s e sl t s u n e b e a s ni l h h s y y s m yi s o n o i n o t s l A l a l n ri t o b a R A a n m a a e t n t a ci a t a e H P r a n a e a e r c a L s ma o f m r A e a ei ul t r q e o , e T t e al a m h f s c N t n e n E r e rf r r s e M r o da f a i y r N e e , O s t s nn s s l e R o a e o e c ei sh af n e I d h d il i V /t / t af yt aR e e c ci l ( N E s r s a c af ni I I t o o o rd e df r p a s d f s d a i s I e I eh I n o e I m I h t r I o h h i t o i t t d t d ,dn f d t e r o o o a M o h e h s ad e . h c N t r t r t o l e u e ed t s M el l e ah M s M t n s u o r ar cjn o u s m t r p rr r o x o u ed e o a o n F i F e F q s a c Ff O s e ) ) ) t ) o 1 2 ( 3 ( 4 ( N ( TABLE B.7-3 USACE FACTORS FOR VARIOUS GASEOUS PATHWAYS AT SEABROOK STATION (from Reference A, Table E-5)* Maximum Recentor: i Age Leafy SI9.9.2 Veretables Venetables Hilk Haag Inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m8 /yr) Adult 520.00 64.00 310.00 110.00 8000.00 Teen 630.00 42.00 400.00 61.00 8000.00 child 520.00 26.00 330.00 41.00 3700.00 Infant 0.00 0.00 330.00 0.00 1400.00 The " Rocks" and Science & Nature Fenter* Age Leafy l Group Veretables Veretables gilk ggg.g Inhalation l (kg/yr) (kg/yr) (1/yr) (kg/yr) (m8 /yr) l Adult 0.00 0.00 0.00 0.00 8000.00 j l Teen 0.00 0.00 0.00 0.00 8000.00 l Child 0.00 0.00 0.00 0.00 3700.00 l Infant 0.00 0.00 0.00 0.00 1400.00 O V

Regulatory Guide 1.109 B.7-33 ODCM Rev. 16

l 7.3 RECEPTOR POINTS AND AVERACE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATINAYS The gaseous effluent dose equations (Method I) have been simplified by casuming an individual whose behavior and living habits inevitably lead to a higher dose thaa anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:

1. Direct exposure to contaminated air;

2. Direct exposure to contaminated ground;

3. Inhalation of air; .

4. In5estion of vegetables;

5. Ingestion of goat's milk; and 1

6. Ingestion of meat.

Ssetion 7.3.1 details the selection of important off-site and on-site locations and rsceptors. Section 7.3.2 describes the atmospheric model used to convert =oteorological data into atmospheric dispersion factors. Section 7.3.3 presents the maximum atmospheric dispersion factors calculated at each of the off-site receptor ' locations. 7.3.1 Recentor Locations The most limiting site boundary location in which individuals are, or likely to be located as a place of residence was assumed to be the receptor for all the I g:seous pathways considered. This provides a conservative estimate of the dose to en individual from existing and potential gaseous pathways for the Method I cnalysis. This point is the west sector, 974 meters from the center of the reactor units for undepleted, depleted, and gamma X/Q calculations, and the northwest section, 914 meters for calculations with D/Q the dispersion parameter. The site boundary in the NNE through SE sectors is located over tidal marsh (e.g. , over water), and consequently are not used as locations for determining maximum off-site receptors (Reference NUREG 0133). g, B.7-34 ODCM Rev. 16 7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS 7.3.1 Recentor Imcations (Continued) Two other locations (on-site) were analyzed for direct ground plane exposure l and inhalation only. They are the " Rocks" (recreational site) and the Education Center shown on Figure 5.1-1 of the Technical Specifications. 7.3.2 Seabrook Station Atmosoheric Disnersion Model The time average atmospheric dispersion factors for use in both Method I and ! Method II are computed for routine releases using the AEOLUS-2 Computer Code (Reference B). AEOLUS-2 produces the following average atmospheric dispersion factors for each location: l

1. Undepleted X/Q dispersion factors for evaluating ground level concentrations of noble gases; i

2. Depleted X/Q dispersion factors for evaluating ground level concentrations of iodines and particulates;

3. Gamma X/Q dispersion factors for evaluating gamma dose rates from a sector averaged finite noble gas cloud (multiple energy undepleted source); and

4. D/Q deposition factors for evaluating dry deposition of elemental radioiodines and other particulates.

Gamma dose rate is calculated throughout this ODCM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5). That model is implemented through the definition of an effective gamma atmospheric dispersion factor, [X/Q1) (Reference B, Section 6), and the replacement of X/Q in infinite cloud dose equations by the [X/Q1) . 7.3.3 Averare Atmoseheric Disnersion Factors for Recentors The calculation of Method I and Method II atmospheric diffusion factors (undepleted CHI /Q, depleted CHI /Q, D/Q, and gamma CHI /Q values) utilize a methodology generally consistent with US NRC Regulatory Guide 1.111 (Revision 1) criteria and the methodology for calculating routine release diffusion factors as l represented by the XOQD0Q computer code (NUREG/CR-2919). The primary vent stack is ^ treated as a " mixed-mode" release, as defined in Regulatory Guide 1.111. Effluents are considered to be part-time ground B.7-35 ODCM Rev. 16 7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIu DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS 7.3.3 Averare Atmospheric Dispersion Factors for Receptors (Continued) isvel/part-time elevated releases depending on the ratio of the primary vent stack offluent exit velocity relative to the speed of the prevailing wind. All other rolease points (e.g. , Turbine Building and Chemistry lab hoods) are considered ground-level releases. In addition, Regulatory Guide 1.111 discusses the concept that constant mean wind direction models like AEOLUS-2 do not describe spatial and temporal variations in airflow such as the recirculation of airflow which can occur during prolonged p2riods of atmospheric stagnation. For nites near large bodies of water like Scabrook, the onset and decay of sea breezes can also result in airflow reversals cnd curved trajectories. Consequently, Regulatory Guide 1.111 states that cdjustments to constant mean wind direction model outputs may be necessary to cecount for such spatial and temporal variations in air flow trajectories. R2 circulation correction factors have been applied to the diffusion factors. The rscirculation correction factors used are compatible to the " default open terrain" racirculation correction factors used by the XOQDOQ computer code. The relative deposition rates, D/Q values, were derived using the relative dsposition rate curves presented in Regulatory Guide 1.111 (Revision 1). These curves provide estimates of deposition rates as a function of plume height, stability class , and plume travel dictance. Recentor Locations I l For ground-level releases, the downwind location of "The Rocks" (244m NE/ENE) l cnd the Science & Nature Center (406m SW) were taken as the distance from the nearest point on the Unit 1 Administrative Building / Turbine Building complex. For the site boundary, the minimum distances from the nearest point on the Administration Building / Turbine Building complex to the site boundary within a 45-degree sector centered on the compass direction of interest as measured from UFSAR Figure 2.1-4A ,ere used (with the exception that the NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations). For primary vent stack releases, the distances fro.n the Unit 1 primary vent stack to "The Rocks" (244m NE) and the Science & Nature Center (488m SW) as measured from a recent site aerial photograph were used. For the site boundary, the minimum distances from the Unit 1 primary vent stack to the site boundary within a 45-degree sector centered on the compass direction of interest as measured from UFSAR Figure 2.1-4A were used (with the exception that the O B.7-36 ODCM Rev. 16 7.3 RECEFIOR POINIS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSU M PATHWAYS 7.3.3 Averare At=ascheric Dinnersion Factors for Recantors (Continued) NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations), gg3;porolorical Data Bases For "The Rocks" and Science & Nature Center receptors, the diffusion factors represent six-year averages durin5 the time period Janusry 1980 through December 1983 and January 1987 through December 1988 (with the exception that, because of low data recovery, April 1979 and May 1979 were substituted for April 1980 and May 1980). For the site boundary receptors, both six-year r.verage growing season (April through September) anC year-round (January through December) diffusion factors were generated, with the higher of the two chosen to represent the site boundary. The meteorological diffusion factor used in the development of the ODCM Method I dose models are summarized on Tables 5.7-4 through B.7-6. O l i B.7-37 ODCM Rev. 16 \ TABLE B.7-4 SEABROOK STATION 1ANG-TERM AVERAGE DISPERSION FACTORS

l PRIMARY VENT STACK O

Dose Rate to Individual Dose to Air Dose to Critical Organ l Total Skin Critical Gamma Beta Thyroid Body Organ 7.5E-07 - - 7.5E-07 X/Q depleted - - - . -07 - X/Q undepleted

1. 5 E - 08** - - 1.5E-08 D/Q ',a '

l s a 's e c' 8.5E-07 8.5E-07 - 8.5E-07 - - 7 - l O l l l 1 i l l l

Urst site boundary, 974 meters from Containment Building

- Northwest site boundary, 914 meters from Containment Building 9t B.7-38 ODQi R ev. 16

TABLE B.7-5 SEABROOK STATION IDNG-TERM AVERAGE DISPERSION FACTORS FOR SPECTAT. (ON-SITE) RECEPTORS PRIMARY VENT STACK Dose to critical Dose Rate to Individual Dose to Air Organ Total Skin critical canna Beta Thyroid Body Organ Education Center: (SW - 488 meters) 1.5E-06 X/Q depleted - - - - 1.6E-06 - X/Q undepleted '1' - - 2.7E-08 - - - D/Q p l 's e e' 1.1E-06 1.1E-06 - 1.1E-06 - - gj , 1 The "Rocksa: (ENE - 244 meters) ~ ~ ~ ~ ~ X/Q deple.ted 's e c' 1.7E-05 - - 1.7E-05 - X/Q undepleted '1' - - 1.1E-07 - - - D/Q p ,, e' 5.0E-06 5.0E-06 - 5.0E-06 - - 7 l O v - 1 l B.7-39 ODCM Rev. 16 i l TABLE B.7-6 SEABROOK STATION IDNG-TERM ATMOSPHERIC DIFFUSION AND DEPOSITION FACTORS CROUND-LEVEL RELEASE PATfNAY R E C E P T 0 R(*) Diffusion Factor The Rocks Science & Nature Off-Site Center Undepleted CHI /Q, 1. 6 x 10** 2.3 x 10-8 1.0 x 10*5 sec/m 3 (244m ENE) (406m SW) (823m W) Depleted CHI /Q, 1.5 x 10-* 2.1 x 10-5 9.4 x 10-8 sec/m 8 (244m ENE) (406m SW) (823m W) D/Q, m-2 5.1 x 10-7 1.0 x 10'? 5.1 x 10-a (244m ENE) (406m SW) (823m W) Camma CHI /Q, sec/m3 2.6 y 10-5 5.3 x 10-8 3.4 x 10-8 (244m ENE) (406m SW) (823m W) i l l l l l l l (*) The highest site boundary diffusion and deposition factors occurred during the l April through September growing season. Note that for the primary vent stack i release pathway, none of the off-site receptor diffusion and deposition factors (located at 0.25-mile increments beyond the site boundary) exceeded the site boundary diffusion and deposition factors. B.7-40 ODCM Rev. 16 8.0 BASES FOR LIQUID AND CASEOUS MONITOR SETPOINTS I 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT k The liquid waste test tank monitor setpoint must ensure that the limits of Technical Specification 3.11.1.1 are not exceeded in combination with any other site discharge pathways. The liquid waste test tank monitor is placed upstream of the major source of dilution flow. The derivation of Equation 5-1 begins with the general equation for the response of a radiation monitor: R=[ C yi Su l (8-1) (cps)= (#ml ) ( tpsd ) l pCi l where: R - Response of the monitor to radioactivity (cps). l Sti - Detector counting efficiency for radionuclide "i" (eps/(pCi/ml)). C,5 - Activity concentration of each gamma emitting radionuclide "i" in the mixture that the monitor has a response efficiency sufficient to detect (pci/ml), ( p The detector calibration procedure for the liquid waste test tank monitor at Seabrook Station establishes counting efficiency by use of a known calibration t , source standard and a linearity response check. Therefore, in Equation 81 one may i l substitute St for S ti , where St is the detector counting efficiency determined from the a alibration procedure. Therefcte, Equation 8-1 becomes: l l R= St E Cy (8-2) (cps)= ( cps-el) { pC1) pCi ml l 1 F l i I l l i i i B.8 1 ODCM Rev. 17 l 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT (Continusd) l The MPC for a given radionuclide must not be exceeded at the point of I discharge to the environment. When a mixture of radionuclides is present, 10CFR20 cpecifies that the concentration (excluding dissolved and entrained noble gases) at the point of discharge shall be limited as follows: l (8-3) [ Cd' s 1 MPC, where: Cai = Activity concentration of radionuclide "i" determined to be present in the mixture at the point of discharge to the environment (pci/ml) . MPCi- The maximum permissible concentration (pCi/ml) for radionuclide "i" from 10CFR20, Appendix B, Table II, Column 2 for all radionuclides except noble gases. The limit for the sum of all noble gases in the waste discharge is 2E-04 pCi/ml (See ODCM Appendix B for listing). The activity concentration of radionuclide "i" at the point of discharge is related to the activity concentration of each radionuclide at the monitor as follows: F l C,- o 4 7, + yi) (8-4) Fo ( pCi) = ( gpm) (pCi) ml gpm ml end with equivalence of Ci - (Cyi + C i), Equation 8 4 can be written as 1 l Cd i = F" Ci

d where:

F. - Flow rate past monitor (gpm) F4 - Flow rate out of discharge tunnel (gpm) l C i - Activity concentration of non gamma emitting radionuclide "i" in I the mixture at the monitor for which the monitor response is inefficient to detect (pci/ml). l Ci - The activity concentration of each radionuclide "i" in the waste stream. This includes both gamma and non gamma emitters , such as tritium, l B 8-2 ODCM Rev. 17 e I 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT (Continued) p Substituting the right half of Equation 8-4 for Cd3 in Equation 8-3, and solving for F 4/F, yields the dilution factor needed to complete Equation 8-3: V DF,in 5 dF C' (8-5) j l F, 2 [, MPC, ( gpa) ( pCi-al ) gpa al-pCi - where: I MPC 3 - The maximum permissible concentration (pCi/ml) for radionuclide "i" from 10CFR20, Appendix B, Table II, Column 2 for radionuclides, i except dissolved and entrained noble gases. For noble gases, a j value of 2E-04 pCi/ml is used for the limit of the sum of noble {' gases in the waste stream. If F 4/F, is less than DL , then the tank may not be discharged until either F4 or F, or both are adjusted such that: (8-5) d DF,1, 5 The maximum allowable discharge flow rate past the monitor can be found by setting Fm to F , and its equivalents, i.e: _ a 8 'f**" DF.1, Usually F4 /F, is greater than DF.1, (i .e . , there is more dilution than necessary to comply with Equation 8-3), but must be satisfied since the monitor can only detect the gamma emitting portion of the waste stream. It is assumed that changes in the expected gamma concentration seen by the monitor from that determined in laboratory analysis are also reflected proportionally in the concentration of non gamma emitters. For tritium, this is conservative since changes in tritium are not affected by those mechanisms, such as crud burst, which could increase particulate gamma emitters. The response of the liquid waste test tank monitor at the setpoint is therefore: - ft x x S { C yi (8-6) R,,epoint y_ y t (cys) () cps-ml pCi () pci , or with F,,, substituted into Equation 8-6 for the maximum allowable discharge flow

1. the setpoint equation can be stated also as:

l rate , DF,t , A l R ,,,,,2,, = f3 x x Sj { Cyj B.8-3 ODCM Rev. 17 l 1 l J 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT (Continuad) where ft is equal to the fraction of the total concentration of MPC at the discharge point to the environment to be associated with the test tank effluent pathway, such that the sum of the fractions of the four liquid discharge pathways is equal to or less than one (f t + f + f + 3 f. $ 1) . The monitoring system is designed to incorporate the detector efficiency, S , t into its software. This results in an automatic readout in pCi/ml or pCi/cc for the monitor response. Since the conversion for changing eps to pCi/ml is inherently done by the system software, the monitor response setpoint can be calculated in l terms of the total waste test tank activity concentration in pCi/mi determined by l the laboratory analysis. Therefore, the setpoint calculation for the liquid wasta test tank is: ~ l F R.,g,, tog - f x v { Cyt t 7_ 7 l ( () () ( ) (5-1) O ODCM Rev. 17 O, B.8-4 1 8.2 BASIS FOR THE PIANT VENT VIDE RANGE GAS MONITOR SETPOINTS ) l The setpoints of the plant vent wide range ps monitors must ensure that l G Technical Specification 3.11.2.1.a is not exceedd Sections 3.4 and 3.5 show that l Equations 3-3 and 3 4 are acceptable methods for de ;.naining compliance with that ! Technical Specification. Which equation (i.e., do w to total body or skin) is more limiting depends on the noble gas mixture. Therefore, e ch equation must be considered separately. The derivations of Equations 5-5 and 5-6 begin with the general equation for the response R of a radiation monitor: R= S,, C,i (3,7) (cpm) = ( cpm-cd) (pCi) pCi cm 3 where: i 1 ( R - Response of the instrument (cpa) { S,1 - Detector counting efficiency for noble gas "i" (cpa/(pCi/cm )) 8 C,1 - Activity concentration of noble gas "i" in the mixture at the noble gas activity monitor (pCi/cm8 ) C.1, the activity concentration of noble gas "i" at the noble gas activity monitor, may be expressed in terms of Qi by dividing by F, the appropriate flow rate. In the case of the plant vent noble gas activity monitors the appropriate flow rate is the plant vent flow rate. C ,, = Qi (8-8)

Ci) ,(pCi) sec) 3 cm 3 sec cm where:

Qg - The release rate of noble gas "i" in the mixture, for each noble gas listed in Table B.1-10. F - Appropriate flow rate (cm8/sec) 1 Substituting the right half of Equation 8-8 into Equation 8-7 for C,i yields: l l l R= S,i di (3,9) (cpm)= ( cpm-cm') (pCi) ( Sec) (A) #Ci sec cm 3 B.8-5 ODCM Rev. 16 8.2 BASIS FOR THE PL/ NT VENT WIDE RANCE GAS MONITOR SETPOINTS (Ctntinuid) As in the case before, for the liquid waste test tank monitor, the plant vent wide range gas monitor establishes the detector counting efficiency by use of a eclibration source. Therefore, S, can be substituted for S,3 in Equation 8-9, where S, is the detector counting efficiency determined from the calibration procedure. Therefore, Equation 8-9 becomes: l R- S, Qi (8-10) 3 (cpm)= ( cpm-cm ) ( sec) (pCi) pCi cm 3 see The total body dose rate due to noble gases is determined with Equation 3-3: 8tb = 0.85

EL(R)

Q, DFB I (3-3) 3 mrem) , pCi-sec) ) gC1) mrem-ct) yr pCi-d sec pCi-yr where:

tb - total body dose rate (arem/yr) 0.85 - (1.0E+06) x (8.5E-07) (pCi-sec/pci-m )8 1E+06 - number of pCi per pCi (pci/pCi) 8.5E-07 - [X/Q)1, maximum off-site average gamma atmospheric dispersion factor (sec/m 8) for primary vent stack releases EL(R) - Release point correction factor - 1.0 for primary vent stack Qg - As defined above. DFB i - total body dose factor (see Table B.1-10) (mrem-m3 /pci-yr) 1 I l l l ODCM Rev. 16 O i B.8-6 l j 8.2 BASIS FOR THE PIANT VENT WIDE RANGE GAS MONITOR SETPOINTS (Continusd) A composite total body gamma dose factor, DFB,, may be defined such that: DFBc[Q i i =[Q i 1 DFB i (8-11) 3 arem-e3 #Ci) (mrem-e y

Ci) ,

pCi-yr pCi-yr sec sec Solving Equation 811 for DFB, yields: y [Q, DFB, ' (5 7) DFB, = bk i t Technical Specification 3.11.2.1.a limits the dose rate to the total body from noble gases at any location at or beyond the site boundary to 500 area /yr. By settin5 btb equal to 500 arem/yr and substituting DFB, for DFB i I in Equation 3-3, one may solve for [ Qg at the limiting whole body noble gas dose rate: i a b I I { Q, = 588 (8-12) i DFB, 3 pCi-yr ( #Ci ) , mrem-#Ci-m ) y sec yr-pCi-sec arem-e3 Substituting this result for [Q i in Equation 8-10 yields Ru,, the response i of the monitor at the limiting noble gas total body dose rate: 1 1 R* = 588 S' F DFB, ( ' (cpm) = (mremfM) ( cM) ( sec)3 ( pCi-yr 3) yr-pCi-sec #Ci cm mrem-m l l O B.8-7 ODCM Rev. 16 8.2 BASIS FOR THE PIANT VENT WIDE RANGE GAS MONITOR SETPOINTS (Centinued) The skin dose rate due to noble gases is determined with Equation 3-4: (3-4) O 6, gin =EL(R)+ {Q i i DF', mrem) , ) (#Ci) { mrem-sec) yr sec pCi-yr where: EL(R) - 1.0 for primary vent stack release (dimensionless) d skin - Skin dose rate (mrem /yr) Qi - As defined above. DF 'i - combined skin dose factor (see Table B.1-10) (arem-sec/gCi-yr) A composite combined skin dose factor, DF',, may be defined such that: DF', EQi i = {I Q, DF'i (8-14) ( mrem-sec) (pCi) , ( pCi ) mrem-sec )

Ci-yr sec sec pCi-yr l

Solving Equation 8-14 for DF' yields: l [i DF', ' (5-8) DF ', = bk i t l B.8-8 ODCM Rev. 16 9 i 8.2 BASIS FOR THE PLANT VENT WIDE RANCE CAS MONITOR SETPOINTS (Centinusd) Technical Specification 3.ll.2.1.a limits the dose rate to the skin from noble L/ gases at any location at or beyond the site boundary to 3,000 mrem /yr. By setting 6, gin equal to 3,000 arem/yr and substituting DF', for DF's in Equation 3-4 one may solve for [ kg at the limiting skin noble gas dose rate: i j I [0,-3,000 0F ,* i (8-15) (#Ci) mrem) ( pCi-yr ) sec yr arem-sec l Substituting this result for [ kg in Equation 8-10 yields R uo, the f I l response of the monitor at the limiting noble gas skin dose rate: 1 1 R, gin = 3,000 S, p, 7 I (cpm) ("#**) (cpm d ) (sec) ( # U -y ) yr pCi cm 3 mrem-sec (8-16) As with the liquid monitoring system, the gaseous monitoring system is also designed to incorporate the detector efficiency, S , into its software. The monitor also converts the response output to a release rate (pci/sec) by using a real time ! stack flow rate measurement input. Therefore, multiplying by the stack flow rate l l measurement (F), the Equations 8-13 and 8-16 become: 1 R= 588 (5-5) DFB, i 3 j pCi ) , mrem-gCi-si ) pCi-yr ) i sec yr-pCi-sec mrem-ni 3 l i 1 R, gin = 3000 (5-6) l DF ,, ; pCi) , mrem) pCi-yr y sec yr arem-sec ! ,Oi ! GI j B.8-9 ODCM Rev. 16 j i l i 8.3 BASIS FOR PCCW HEAD TANK RATE-OF-CHANGE AIARM SETPOINT l l The PCCV head tank rate-of-change alarm will work in conjunction with the PCCW rcdiation monitor to alert the operator in the Main Control Room of a leak to the Ssrvice Water System from the PCCW System. For the rate-of-change alarm, a setpoint btsed on detection of an activity level of 10-sp Ci/cc in the discharge of the Service Water System has been selected. This activity level was chosen because it is the minimum detectable level of a service water monitor if such a monitor were installed. The use of rate-of-change alarm with information obtained from the liquid sampling and analysis commitments described in Table A.3-1 of Part A ensure that potential releases from the Service Water System are known. Sampling and cnalysis requirements for the Service Water System extend over various operating rrnges with increased sampling and analysis at times when leakage from the FCCW to the service water is occurring and/or the activity level in the PCCW is high. O ODCM Rev. 16 O B.8-10 l 8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) The maximum allowable setpoint for the waste gas systes monitors (response in uCi/cm3 ) can be determun,d by aquating the limiting off-site noble gas dose rate from the plant vent to the total oudy or skin dose rate limits of Technical specification 3.11.2.1.a. assuming that .cIl the activity detected by the vent wide-range gas monitors is due to waste gas syster discharges. By evaluating the noble gas radionuclide with the most limiting dose factor as given on Table B.1-10, a conservative activity release rate from the plant vent for both whole body and skin dose rate conditions can be calculated. From Table B.1-10, i l Kr-89 is seen to be the most restrictive noble gas if it were present in the effluent discharge. Applying plant vent setpoint equation 5-5 for the whole body, and equation 5-6 for the skin, the maximum allowable stack release rate can be calculated as follows: Rsb - 588 1/DFB, (5-5) where: Run Pl ant vent maximum release rate (uCi/sec) based on the whole body does rate limit of 500 mram/yr DFB, - 1.66E-02 (arem m 8 /pci-yr), whole body dose factor for Kr-89 g 588 - conversion factor (arem-uCi-m3 /yr pCi-sec) Therefore: Rsb - 588 1/1.66E-02 - 35,421 uCi/see maximum release rate at plant vent Next, the skin dose rate limit is evaluated from equation 5-6 in a similar fashion as follows: R,gi, - 3000 1/DF', (5-6) where: Reti, - ' plant vent maximum release rate (uCi/sec) based on skin dose rate limit of 3000 arem/yr. DF', = 2.45E-02 arem-sec/uCi-yr skin dose factor for Kr-89 3000 - Site boundary skin dose rate limit (arem/yr) B.8 11 ODCM Rev. 16 I i j 8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) (Continued) } therefore: R,m - 3000(mrem /yr) 1/2.45E-02(mrem-sec/uci-yr) - 122,449 uCi/sec from the plant vent Comparing the release rate limit for the whole body to that for the skin (i.e. , 35,421 uCi/see vs 122,449 uCi/sec, respectively) it is determined that the release rate for the whole body is limiting. Next, to get the maximum plant vent release rate from the waste gas system discharge, equate the plant vent maximum release rate limit for the whole body equal to the waste gas system activity concentration times its flow rate to the plant vent, i.e.: l Ra - 35,421(uci/sec) - R,,,(uCi/cm3 ) F,,,(cm3 /sec) or solving for R,,: R,,,(uci/cm8 ) - 35,421(uCi/sec) / F,,,(cm3/sec) R,,, - maximum concentration (setpoint limit) at the waste gas system monitors F,,, - waste gas design flow of 566.4 cm8 /sec (1.2 cfm) therefore: R,,,(uci/cm3 ) - 35,421(uci/sec) / 566.4(cm 3/sec) - 62.5 uCi/cm3 1 This represents the maximum waste gas discharge concentration which would ; aqual the site boun.lary whole body dose rate limit for plant vent releases. Administrative controls may set alert alarm and high alarm (waste gas isolation) ! d setpoints on the waste gas monitors as some multiple of expected activity concentration, such as 1.5 and 2 times, respectively, as long as the maximum setpoint does not exceed 62.5 uCi/cm8 . This provides operational controls to be exercised before any waste gas discharges could equate to the Technical Specification limits of 3.11.2.1.a. I i B.8-12 ODCM Rev. 16 l l 1 8.4 BASIS FOR WASTE CAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) (Continued) [ The primary process monitor noted in Technical Specification 3.3.3.10 is RM- , 6504, which is downstream of the waste gas discharge compressor at the end of the l process system. Monitor RM-6503 is on the inlet side of the compressor downstream ! of the charcoal delay beds, and is considered as an alternate monitor if RM-6504 is inoperable. For the purpose of setting the maximum discharge setpoint, RM-6503 is treated the same as RM 6504, which assumes no additional source reduction before discharge to the plant vent. t u O B.8-13 ODCM Rev. 16 1 i l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) The maximum allowable setpoint for the :nain condenser air evacuation monitor must be cvaluated for two modes of operation. For normal operation.. the monitor is rssponding to a low flow rate that is released through the plant vent stack. During ctart-up (hogging mode), the monitor response must be related to a high flow rate that is being released from the turbine building which is considered a ground level rolease. In both instances, the setpoint can be determined by equating the limiting off-site noble gas dose rate from the release point to the total body or skin dose rates of Technical Specification 3.11.2.1.a. In a manner similar to that for the waste gas monitoring system in $8.4 the most restrictive radionuclide in Table B.1-10, Kr-89, can be used to calculate a conservative activity release rate condition for both total body and skin dose rates. More realistic or actual radionuclide distributions in condenser air can be used to calculate the maximum allowable alarm cetpoint. I.n addition to monitoring the main condenser air, the air evacuation monitor response is also used as an indicator for Turbine Gland Seal Condenser exhaust. Since this is a potential release pathway during both the normal and the hogging codes of operation, the impact is considered in the setpoint calculations. l 8.5.1 Example for the Air Evacuation Monitor Setooint Durine Normal Operations During normal power operation the maximum allowable setpoint for the air evacuation tonitor is determined by applying plant vent setpoint equation 8-13 for the total body, and equation 8-16 for the skin. Therefore, the maximum allowable stack release rate can be calculated as follows: l Ru, - (588) (S ) (1/F) (1/DFB,) (8-13) l (cpm) - (arem-pci-m8 /yr-pci-sec) (cpm-cm8 /pci) (sec/cm 3)(pci-yr/ mrem-m8 ) l where: Ru, - count rate (cpm) for the plant vent maximum release rate based on the total body dose rate limit of 500 mrem /yr 588 - conversion factor (arem pci-m 8 /yr-pCi-sec) S, - the detector response efficiency (cpm-cm8 /pCi) as determined from monitor calibration. For the air evacuation monitor, a typical ; value is 6.0E+05 epm-cm 8/pci. - F - release flow rate. During normal operations, a typical flow value is 4.72E+03 cc/sec (10 cfm) for the air evacuation pathway. DFB, - the composite total body dose factor, For Kr-89 alone, the value is 1.66E-02 (arem-m 8 /pCi-yr) . For different gas mixes, the composite can be found from: l DFB, = [h DfB i i / [k t (5-7) i i i O B.8-14 ODCM Rev. 16 l l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) l 8.5.1 Examole for the Air Evacuation Monitor Setooint Durine Normal Operations ('] (Continued) LJ l Therefore, l Ra, - 588 6.0E+05 (1/4.72E+03) (1/1.66E-02) - 4.50E+06 cpm detector count rate for a maximum release rate st the plant vent based on the total body dose rate. Next, the off-site skin dose rate limit is evaluated from equation 8-16 in a similar fashion as follows: l Rm, - 3000 S (1/F) (1/DF',) (8-16) l (epm) - (arem/yr) (cpm-cm3 / Ci) (sec/cm 8) (pCi-yr/ mrem-sec) l where: Rmn - count rate (cpm) for a plant vent maximum release rate based on the l skin dose rate limit of 300 mrem /yr DF', - the elevated release skin dose factor for Kr-89 of 2.45E-02 (mrem-sec/pci-yr). eN l Therefore, l Q"'j Rmo - 3000 6.0E+05 (1/4.72E+03) (1/2.45E-02) - 1.56E+07 cpm detector count rate for a maximum release rate at the plant vent based on the skin dose rate. Comparing the release rate limit for the total body to that of the skin (i.e. , 4.50E+06 cpm versus 1.56E+07 cpm, respectively) it is determined that the release rate for the total body is limiting in this case. Since during normal operations the Turbine Gland Seal Condenser exhaust has the potential to be a minor additional contribution to the plant vent release, the effective contribution from the main condenser exhaust must be limited to some fraction of the calculated value. The contribution from the Turbine Gland Seal Condenser exhaust is expected to be minor because this system handles only 670 lbs/ hour of steam which is a very small fraction of the 1.5E+07 lbs/ hour of secondary side steam that the main condenser handles. Therefore, the maximum alarm is set at 3.2E+06 cpm, which is 70% of the calculated value, to ensure that the contribution of the two does not exceed the dose rate limit of Technical Specifications 3.11.2.1.a. During normal operations, this would represent the maximum allowable count rate on the air evacuation monitor that would equate to the site boundary total body dose rate limit or less. 7q \ ) v B.8-15 ODCM Rev. 16 I 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) 8.5.2 Examole for the Air Evacuation Monitor Settoint Durine Start Uo (Horrine Mode) During start up (hogging mode), the determination of the air evacuation setpoint must take into account a larger air flow rate that is also released as a ground icvel effluent. The flow rate must also include the contribution from the Turbine Gland Seal Condenser exhaust, which is a potential release pathway which the air svacuation monitor response must also take into account. For ground releases, the ! g neral equation 8-10 is used to represent the monitor count rate. l l R - (S ) (1/F) [Qg (8-10) { (cpm) - (cpm cm3 /pci) (sec/cm8 ) (pci/sec) where: I l R - detector count rate (cpm) ) 1 3 S. - the detector efficiency (cpm cm /pci) l F - release flow rate (cm 8/sec) l kg - the release rate of noble gas "i" in the mixture, for each noble gas listed in Table B.1-10. For a ground release, the off-site total body dose rate is based on: I D tb(s) = 3.4 [(Q ei DFB i ) (3-3b) i A composite total body dose factor, DFB, can be defined such that: l DFBc [h i [ (kg DFBg) (8-11) i i l I l B.8 16 ODCM Rev. 16 1 f l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) l 8.5.2 Examnie for the Air Evacuation Monitor Setooint Durine Start Un (Horrine Mode) (Continued) l By substituting 8-11 into 3-3b and rearranging to solve for [Q i the following i l equation is obtained: l l [d i ( ctw,3 /3.4) (1/DFB,) i By inserting a limiting value of 500 mrea/yr as two) this simplifies to: i l { d, - 147 (1/DFB,) i l Insertion of this equation into equation 8-10 yields: Ol R m ,3 - 147 Sc,3 (1/F) (1/DFB,) l (cpm) - (arem-pCi m3 /yr pCi-sec) (cpm-cm3 /pCi) (sec/cm3 ) (pCi yr/arem-m3) l 1 I l where: Rec,3 - count rate (cpm) for the maximum ground release rate based on the l total body dose rate limit of 500 are/yr. l 147 - conversion factor (arem-pCi-m 3/yr-pCi-sec) S, - the detector response efficiency for the air evacuation monitor (a typical value of 6.0E+05 cpm-em 8 /pci is applied in this example) . O ODCM Rev. 16 B.8-17 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) 8.5.2 Example for the Air Evacuation Monitor Setooint Durine Start Uo (Horrine Mode) (Continued) l F - release flow rate. During the hogging mode of operation, a value 8 of 5.57E+06 cm /sec (1.18E+04 cfm) is assumed. This value represents the sum of the 1.0E+04 cfir from the main condenser discharge and the 1.8E+03 cfm exhaust rate from the Turbine Gland Seal condenser. Both discharges are to the Turbine Building roof. DFB, - the total body dose factor from Table B.1-10. For Kr-89, this factor 8 is 1.66E-02 (arem-m /pCi-yr) . l Therefore: Ruits) 147 6.0E+05 (1/5.57E+06) (1/1.66E-02) - 9.54E+02 cpm detector count rate for a maximum ground release rate based on the total body dose rate. Next, the off-site skin dose rate limit for a ground release in evaluated from squation 3-4b in a similar fashion as follows: l 1 I I b skin (s) ~ (i Of(s)) i (3-4b) i l A composite skin dose factor, DF',c,3 can be defined such that: l DF' oc,3 { Q, - [ (Q, DFic,3) (8-17) i i l By substituting 8-17 into 3-4b and rearranging to solve for [h i the 1 l following equation is obtained: ! bhi i " b skince) (1/DF',c,3) l l By inserting a limiting value of 3000 mrem /yr as skin (s) this simplifies to: O B.8-18 ODCM Rev. 16 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) 8 . 5 . 2 5'v =nl e for the Air Evacuation Monitor Setnoint Durine Start Uo (Horrine Mode) (Continued) l { Q, - 3000 (1/DF',c,3) i I l Insertion of this equation into equation 8-10 yields: l R*i" - 3000 S. (1/F) (1/DF',c,3) l (cpm) - (ares /yr) (cpa-cm8 /pci) (sec/cm8 ) (pCi-yr/arem-sec) l where: Ratoc,3 - Count rate (cpa) for the maximum ground release rate based on the skin dose rate limit of 3000 mrem /yr. DF ' , c,3 - the ground release skin dose factor from Table B.1-10. For - Kr-89, this factor is 1.67E 01 (arem-sec/p/Ci-yr). (~T Therefore: U Rat.c,3 - 3000 6.0E+05 (1/5.57E+06) (1/1.67E-01) 1.94E+03 cpm detector count rate for a maximum ground release rate based on the skin dose rate. l Comparing the release rate limit for the total body to that of the skin (i.e., 9.54E+02 eps versus 1.94E+03 cpm, respectively) it is determined that the release rate for the total body is limiting in this case. During start up (hogging mode), I I this represents as a 8round level release the maximum allowable count rate on the air evacuation monitor that would equate to the site boundary total body dose rate limit. Since during startup, the plant vent still constitutes a primary release pathway, the effective contribution from the hogging exhaust must be limited to some fraction of the calculated value to ensure that the combination of all gaseous , releases from the station do not exceed the dose rate limits of Technical l Specification 3.11.2.1.a. In this example, the maximum alarm point is set at 15% of the calculated value, or 1.4E+02 cpm. I O ODCM Rev. 16 B.8-19 I REFERDiCES A. Regulatory Gu'de 1.109, " Calculation of Annual Doses to Man From Routine , Releases of Reactor Effluents for the Purpose of Evaluating Compliance with l 10CFR50, Appendix I", U.S. Nuclear Regulatory Commission, Revision 1, October 1977. l B. Hamawi, J. N., "AEOLUS A Computer Code for the Determination of Continuous and Intermittent-Release Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents in Open-Terrain Sites, Coastal Sites, and Deep-River Valleys for Assessment of Ensuing Doses and Finite-Cloud Gamma Radiation Exposures," Entech Engineering, Inc., March 1988. C. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases From Light-Water Cooled Reactors", U.S. Nuclear Regulatory Commiscion, March 1976. D. National Bv Jau of Standards, " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure", Handbook 69, June 5,1959. E. Slade, D. H., " Meteorology and Atomic Energy - 1968", USAEC, July 1968. ( F. Seabrook Station Technical Specifications. ( l l 5 ( R-1 ODCM Rev. 16 APPENDIX A O i DOSE CONVERSION FACTORS O O A-1 ODCM Rev. 16 APPENDIX A METHOD I DOSE CGWERSION FACTORS

1. LIQUID PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from effluents into liquids is derived from Appendix A of Reg. Guide 1.109. Since Seabrook is a salt water site, the assumed pathways of exposure taken from Reg Guide 1.109 are Aquatic foods -

fisn; Aquatic foods -invertebrates; and dose from shoreline deposits (direct dose). No drinking water or irrigation pathways exist because of the salt water cnvironment. In addition, exposures resulting from boating and swimming activities have been included for key radionuclides even though Reg. Guide 1.109 identifies these pathways as not contributing any significant contribution to the total dose, tnd therefore does not provide dose equations for them. For completeness, the cwimming and. boating pathways have been included using the dose models from the HERMES code (HEDL-TME-71-168, Dec.1971) section G, Water Immersion. The Method I dose conversion factors are derived by calculating the dose impact to individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by radionuclide are calculated for each of the 7 organs (including whole body) for each of the four age groups (adult, teen, child, cnd infant). The Method I dose factor for each nuclide is then selected by takir.g the highest factor for any organ in any of the age groups for ar the exposure pathways combined. The list of dose factors in the ODCM then represents a combination of different limiting organs and age groups which, when used to calculate a dose impact from a mix of radionuclides released in liquid effluents, gives a conservative dose since it combines the exposure to different organs and age groups as if there was a single critical organ-age group. As an example of how the liquid dose conversion factors are developed, the following calculation for Co-60 is shown. The critical organ / age group is selected based on the full assessment of all organs and age groups. Factor for fish Ingestion: The general equation for ingestion doses in RG 1.109 is eq. A-3. 1119.7 e **

Qi eB,p *D,ipj ee %

The full assessment for the ODCM dose factors indicated that for i - Co-60, the maximum dose (mrem /yr) is to the GI-LLI of an adult as the target organ and age group, therefore: A-2 ODCM Rev. 16 l l l U,, :- 21 kg/yr cdult usr53 fcctor for fish M, :- 0.1 mixing ratio for near field dilution provided by y submerged multiport diffuser. F :- 918 cu. ft./se.c effluent flow rate for circulating water system Qi :- 1.0 curies / year released of CO-60 assumed B,3

- 100 equilibrium bioaccumulation factor for CO-60 in salt water fish, in liters /kg D.i,3 :- 4.02

10-5 aren/pci. adult GI-LLI ingestion dose factor from RG-1.109, table E-11.

A :- 1.501

10-5 decay constant for CO-60 in 1/ hrs.

t, :- 24 time between release and ingestion, in hrs. 1119.7 is the factor to convert from Ci/yr per ft3/see to pCi/ liter. Note that RG 1.109 uses 1100 as a rounded approximation. [ Therefore the dese from fish to adult GI-LLI is (arem/yr): 1119.7 +

Qi *B i, *D ,ip; *e* * - 0.0103 l

Factor for invertebrate ingestion: Next, the dose from invertebrates to the adult GI LLI is given by the same general equation but with the following variables changed: O ODCM Rev. 16 A-3 U, r

- 5 kg/yr ustga frcter B,

3

- 1000 1/kg bioaccumulation factor all other variables the same as above therefore the dose from invertebrates is (area /yr):

1 1119.7 + * + Q,

Bip *D,ip;

e "a = 0.0245 Fector for shoreline direct dose:

The general equation for direct dose from shoreline deposits is taken from equation A-7 in RG-1.109 as (mrem /yr):

+ Qi *T

D,,p; e *"' + 1 -e-*"*

111970 + , It is assumed that all internal organ doses also receive exposure from direct external sources, therefore each organ dose due to ingestion must have an external component added. For the above equation, the site specific variables for an adult exposure to a 1 curie per year release of CO-60 are: U., :- 334 hrs / year usage factor used for assumed shoreline activities at Seabrook. Mp :- 0.1 mixing ratio for near field dilution provided by the submerged multiport diffuser and assume to be extended to the beach continuously. W := 0.5 shorewidth factor for ocean sites, dimensionless I I l l ODCM Rev. 16 A-4 T :- 1.923*108 redicactiva htlf life in dtys for CO 60 3 D i,3 :- 1.70*10** dose factor for CO 60 due to deposits in I sediments, units of (arem/hr)/(pCi/m2) ep :- 0.0 transit time to point of exposure, hrs i tb :- 131400 period that sediment is assumed to be exposed to water contamination for long term buildup, set at 15 years for Method I DCF's 1 Qi :- 1.0 curies per year, Co-60 assumed l l 111970 conversion factor to convert (Ci/yr)/(ft3/sec) to pCi/ liter and account for the proportionality constant used in sediment model Therefore the dose to the whole body and each organ due to direct exposure to the shoreline (arem/yr) is: l 111970 + + Qi *T+D ,,3

e "' + 1-e'*"* =0. 0573 O

V Direct dose due to Swimmin5: The dose due to immersion in water (swimming) is taken from the HERMES computer code. The original ODCM calculation was based on some preliminary dilution assumptions which gave a near field prompt dilution factor for the multiport diffuser of 8. For single unit operation with both service water and circulating water flow (412,000 gpm), a value of 10 is more realistic. This surface area of the plume is restricted to a small area over the diffuser and does not touch the shoreline approx. 1 mile away. Since the over all impact from swimming is small when compared to the other exposure pathways, the original conservatism on dilution are kept here. O A-5 ODCM Rev. 16 Tha dono from zwimming is giv:n by tha following equatien:

DF,, (arem/yr) 1.0 1012 * * [iQ a

Where: Up := 45 hrs /yr, usage factor for swimming for maximum age group (teen) from HERMES. F. :- 6.56*10u liters /yr, estimated annual dilution effluent flow in multiport diffuser Qi :- 1.0 Curies /yr, assumed release rate of nuclide 1. DFi , :- 4.6*10-8 mrem-liters per hrs-pci, dose factor for Co-60 for water immersion taken from HERMES. 1.0*10u constant for pCi/Ci Therefore the swimming dose for a 1 curie release of Co-60 is (mrem /yr): 4 O 1.0*1012

Up *

Q i *DF,, - 3.155*10 l

As can be seen, the contribution of the swimming dose is only about one 30000ths of I the total of the RG 1.109 pathways, and can be 15nored in the case of Co-60. Similarly, the boating dose as given in HERMES is taken as half of the swimming dose, (and corrected for change in usage assumptions) . The resulting dose is found to be less than the swimming dose and sn also therefore be discounted in this case. ODCM Rev. 16 O A-6 Totsi liquid P:thwsy d:co: The sum of the above liquid pathway doses can now be added to give the total b) ( j maximum individual dose to the critical organ (adult-GI-LLI) for Co-60. This l gives: l ! 0.0103 + 0.0245 + 0.0573 - 0.0921 arem/:*r 1 1 Since the internal doses given by the RG-1.109 methods actually are 50 yr dose commitments resulting from one year exposure to the quantity of activity assumed to be released into the water, and the direct dose represents the dose received for the period assumed to be exposed to the pathway, and the activity release was taken as a unit quantity (i.e. Q - 1 Ci), the above total liquid pathway dose can be stated as site specific committed dose factor in mrem /Ci l released. For Method I in the ODCM, the critical organ dose factor is seen to be 0.0921 arem/C1, as shown above. The value reported on Table B.1-11 (9.22 E-08 mrem / C1) was generated by a computational routine which gives rise to the round-off difference between it and the above example. The whole body site specific dose factor for the ODCM was calculated in the same way treating g the whole body as a separate organ. b l l l l t l l l / \ A-7 ODCM Rev. 16 l l l l II. GASEOUS PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from gaseous effluents in the form of iodines, tritium, and particulates are derived from Appendix C of Reg. Guide 1.109. For Seabrook, it is assumed that at the off site location which exhibits minimum etmospheric dilution for plant releases the following exposure pathways exist: inhalation, ground plane, ingestion of goats milk, meat, stored vegetables, and Isafy vegetables. The Method I dose and dose rate factors are derived by calculating the dose impact to all age group individuals via the site specific pathways for a unit activity rolease (1 curie per nuclide). For each pathway, doses by nuclide are calculated for each of 7 organs (including the whole body) for each of the 4 age groups. The M2thod I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all exposure pathways combined. The list of dose factors in the ODCM then represents a combination of different limitin5 organs and age groups which, when used to calculate the dose impact from a mix of rcdionuclides released into the atmosphere, gives a conservative dose since it ccmbines the exposure to different organs and age groups as if they were for all the came critical organ-age group. As an example of how the gaseous particulate dose factors are developed, the following calculation for Kn-54 is shown. The critical organ / age group for Mn-54 was selected based on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary (max. dose point due to meteorology), the critical organ and age group for Mn-54 was ; determined to be the GI-LLI for the adult. PART A: INHA1ATION DOSE CONTRIBUTION The general equations for inhalation doses in RG 1.109 are eq. C-3, and C-4 which together give: 3 .17 + 10

R,* 3 * [ Q *DFA i ij, = 0;,

Q i Where for the case of Mn-54 releases, the variables above are defined as: 3.17*10' is the number of pCi/Ci divided by the number of second per year ODCM Rev. 16 O A-8 R. :- 8000 th2 bracthing rate for a.gs group a (cdults) in n a 3 /yr. O - x

- 7. 5

10~7 the long term average depleted atmospheric 0 dispersion factor, in sec/m*3, at the maximum exposure point off site (S.B.)

Qi :- 1 the release rate of nuclide i to the atmosphere in Ci/yr DFAg. :- 9.67*10-s the inhalation dose ator for nuclide 1 (Mn-54), organ j (GI-III), and age group a (adult) taken from RG 1.109, table E-7, in mrem /pci inhaled. Therefore, the inhalation dose to the maximum potential off site individual is given as: l l 'X' 3.17*10'eR, . .Q i. DFA ij , = 0.00184 mrem /yr per Ci 0 l PART B: GROUND PIANE DIRECT DOSE CONTRIBUTION The general equations for ground plane external direct dose in RG 1.109 are equations C-1 and C-2 which together give the dose DG as: 8760 1.0+10 12 ,3, , '[ 0 , { g, , I M

DFG At ij I

Where for the case of Mn-54 releases, the variables in the above equation are defined as: O ODCM Rev. 16 i A-9 1.0010 12 is tha numbar cf pCi par Ci Sr :- 0.7 the shielding factor provided by residential structures (dimensionless) for use in calculation accumulated doses over time. Nete that for determination of dose rate factors (i.e. instantaneous dose rates) the shielding factor is set l equal to 1.0, or in affect no credit for dose reduction is taken for determination of dose rates at points in time. D - :- 1.5*10-s the long term average relative deposition factor at 0 the maximum site boundary location, in 1/m^2 1 At :- 0.8105 is the radiological decay constant for Mn-54 (nuclide f i in this case) in 1/yr. j l t3 :- 15 is the time in years over which accumulation is l I evaluated (approx. midpoint of plant operating life) !

= 5.80*10-8 external dose factor to the whole body, or DFGi3 any internal organ j, for standing on contaminated ground from Mn-54 (RG 1.109 Table E-6) in mrem /hr per pCi/m*2 Qi := 1.0 is the unit release quantity assumed for each nuclide i, in Ci/yr.

8760 is the number of hours in a year Therefore, the contributie.n to the total dose made by exposure to the ground plane et the maximum off site exposure location for Mn-54 is given as: 8760+1,0+10 12 S,

E *Q,

D -4.t' *DFGy = 0.658 mrem per yr per Ci 0 1 ODCM Rev. 16 O

A-10 , l PART C: INCESTION DOSE CONTRIBUTION: ( ^" '" i"i*i'1 ***" * #***""i i"' *h* # ** "'#'"ib"*i " #" " i **' i " f "i*k' meat, stored vegetables, and leafy vegetab*ies, we mtst first calculate the l radionuclide concentration in forage, produce, and leafy vegetables resulting from i l atmospheric tranfers of the activity to the surface of the vegetation and onto the I soil for root uptake. For all radioiodines and particulate nuclides (except tritium and C-14), the concentration of nuclide i in and on the vegetation at a point of interest can be calculated using R.G.1.109 equations C-5 and C-6, which combined l gives: l 1 1.14 10s , 'p '

Q e r*I '

e -A * *

i Yy *A + Bi '

IP-** A, Q gi l

l l l PART C.1: ,oncentration in Produce (stored veretables) h For the case of Mn-54 released in air emissions to the maximum site boundary, the d concentration of Mn in produce grown in the hypothetical garden at that location can be calculated from the above equation where the variables are defined as: 1.14*10s is the number of pCi per Ci divided by the number of hours in a year (8760). E=1.510 4 is the relative deposition factor, in 1/m2, at the O maximum exposure point off site (S. B.) Qi := 1 the release rate of nuclide i to the atmosphere in Ci/yr r :- 0.2 fraction of deposited activity retained on crops, leafy vegetables, or pasture grass (1.0 for iodines) ) %/ A-11 ODCM Rev. 16 1 Ari :- 0.00219 effsetiva remov21 rato constcnt for Mn-54 free crops due to decay and weathering, in br-1 tb := 131400 soil exposure time to deposition, in (equal to 15 yrs, or mid plant life) Y, := 2.0 agricultural productivity (yield) for produce, in kg/m-2 B,1 := 2.9*10-2 concentration factor for uptake of Mn-54 from soil by edible parts of crops in pCi/kg (wet weight) per pCi/kg dry soil Ai :- 9.252*10-s radioactive decay constant for Mn-54, in hrs-1 P :- 240 effective surface density of soil, in kg/m2 t3 := 1440 crop holdup time after harvest and before ingestion, in hrs t, := 1440 crop exposure time to plume, in hrs Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as: .t* I *-z r.**q .t' 1.14 10s , p . Q, + +Biy * .e ~A***- 67.379 pci/kg Y*A v Ei P + A, _ Q. , PART C.2: 14afv veretable concentration For leafy vegetables, the above equation is repeated with the value for t.h, crop holdup time after harvest is changed from 1440 hrs to 24 hrs, i.e. : ODCM Rev. 16 O A 12 th :- 24 crap holdup time eftor hervast, in i:rs. Therefore the concentration of Mn 54 in leafy vegetables at the maximum deposition point due to a unit activity release is given as: 1 1 - ~ D 1 -4 *t- -4et 1.14 10s , ,q, p, + B,, . I .e i "" - 76.811 pci/kg l PART C.3.a: Animal Feed concentration (easture): C, Next, we can repeat the above calculation to determine the concentration of Mn-54 in pasture grass used as animal feed. This will allow for the determination of dose contribution from milk and meat. For pasture grass, all the above variables remain the same except for: Y, :- 0.70 for agricultural productivity of pasture grasses, kg/m2 t, :- 720 for grass exposure time to plume, hrs th :- 0.0 for holdup time after harvest 1 Using these variables in the abcve equation gives the concentration in pasture grass as: 1 -e~k "* 1.1410s,"p",g,, p, +B iy . I .e 4 "a - 179.227 pci/kg 0 Yv

ki P

A,

( \ A-13 ODCM Rev. 16 I l l PART C.3.b: Animal Feed Concentration (stored feed): C, i Fer stored feed that would be given to goats, or meat animals, the average c:ncentration would be calculated by changing the following variables in the above cciculation to: Y, :- 2.0 agricultural productivity for stored feed t, := 1440 feed crop exposure time to plume in hrs tg := 2160 feed crop holdup time after harvest, hrs Putting these values back into the above equation gives the concentration in stored cnimal feed (goat and meat animal) of Kn-54 for a unit activity release to the motimum exposure point. 14 4 .t* c' 1.14 10s , p , g, , p, + B,*

1 * -z .e -A ** * = 63 . 03 7 pCi/kg Q Y,

Ag P+A i PART C.3.c.: Concentration in coat's Milk: C.

The Mn-54 concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated from RG 1.109 general equation C-10 as: F, C, + Q, e e-A **' - cone. in milk, pCi/ liter ( A-14 ODCM Rev. 16 O 1 l f 1 q l wh::re ths varichiss era defin:d cs: I F, := 2.5*10-' average fraction of animal's daily intake of Mn-54 ) which appears in each liter of milk, in days / liter Q, :- 6.0 amount of feed consumed by a goat per day, in kg/ day (50 kg/d for meat) tr :- 2.0 average transport time of activity from f eed into j milk and to receptor, in days. A3 :- 2.22*10-8 decay constant of Mn 54, in days-1 In addition, the C, term for the concentration of a nuclide in the animal's feed is l given from RG 1.109 general equation C-11 as: l C, = f, e f,

C, + [1-f,] +C, + f, * [1 -f,] +C, A

where ths following equals: f, :- 0.5 fraction of the year that animals graze on pasture f, :- 1.0 fraction of daily feed that is pasturs gfiis Whsn the animal grazes on pasture C, :- 179.227 concentration of Mn-54 in pasture grass as calculated from above, pCi/kg C, :- 63.037 concentration of Mn-54 in stored feed as calculated from above, in pCi/kg Therefore, the concentration in the total animal's feed is estimated to be: 'O A-15 ODCM Rev. 16 f, +f, *C, + [1-f ]p *C, + f, * (1-f,] *C, = 121.132 pCi/kg When this value of 121.132 is put back into the above general equation for nuclide - csneentration in milk, we get: l pC1/kg j [Cy :- 121.132 ] I j rnd l l F, + Cy + Q,

e-A **' = 0.181 pci/ liter of Mn-54 in goats milk f PART C.3.d.: Concentration in Meat: Cr Similar to milk, the concentration of the nuclide in aninal meat is calculated. RG 1.109 general equation C-12 is given as: J i

C, = F,

C,

Q, e e-A *** f Here the variables are set as: !

Fr :- 8 . 0*10-* fraction of animals daily intake of Mn-54 which appears in each kg of flesh, in days /kg Qy :- 50.0 animal's daily feed intake, in kg/ day t, := 20.0 average time from slaughter to consumption, in days , l C, := 121,132 concentration on Mn-54 in animal's feed, same as ! calculated above for goat, in pCi/kg Therefore, the concentration of Mn-54 in animal meat is calculated to be: ODCM Rev. 16 O A-16 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ F, .Cy *Q, ee4 "a - 4.635 pci/kg in meat for Mn-54 PART D: DOSE FROM INGESTION OF FOODS PRODUCED AT MAXIMUM LOCATION Now that we have calculated the concentration of Mn-54 in milk, meat, leafy vegetables, and stored vegetables produced at a location of maximum air deposition, the resulting dose to any organ j and age group a can be calculated from the following general equation C-13 taken from RG 1.109: l [ DFIq, [ Uy , e f, *C y + U,,

C, + U,, *C, + Ut , e f3 Cg ]

l t l l l For Mn-54 set equal to 1, we find that from the evaluation of all organs for all age Broups for combination of all exposure pathways, the adults GI-LLI is the critical age group / organ. Therefore, the variables in the above dose equation can be defined as: l /* I, DFIo, := 1.40*10-5 ingestion dose factor for adults /GI-LLI for Mn-54, in mrem /pci ingested (RG 1.109, Table E-11) Uy, :- 520.0 vegetable ingestion rates for adults, kg/yr l 1 f, :- 0.76 fraction of stored vegetables grown in the garden 1 f2 := 1.0 fraction of leafy vegetables grown in the garden l l U,, :- 310.0 milk ingestion rate for adults, liter /yr %d) A-17 ODCM Rev. 16 l l Ura :- 110.0 mert ingsetien rato for cdulto, kg/yr U. t :- 64.0 leafy vegetable ingestion rate for adults, kg/yr C, :- 67.379 concentration of Mn-54 in stored vegetables , in pCi/kg (from above) C, :- 0.181 concentration of Mn-54 in milk, in pCi/ liter (from above) Cr :- 4.635 concentration of Mn-54 in meat, in pCi/kg (from above) Ct :- 76.811 concentration of Mn-54 in leafy vegetables , in pCi/kg (from above) The dose from the combination of ingestion pathways for this example is calculated by substituting the above listed variables back into the ingestion dose equation: O DF gI , * (V,, e f,

C, + V,,

C, + U,,

C, + U t, e f,

C ]g = 0. 4 495 mrem-/yr per Ci By breaking the above dose equation down into the different pathways which combine to give the total ingestion dose, we can see the individual dose contribution made by each exposure pathway.

Therefore, we have: Dose for ingestion DFIy *U,, *f, *C, - 0. 37 3 ; of stored vegetables Dose for ingestion DFIy *U., *C, - 7.855*10-' of goat's milk l A-18 ODCM Rev. 16 l Doso for ingsstien DFIy, *Ur. *Cr - 0.00714 of meat l O lb l Dose for ingestion DFIy *Ut ,. *ft *Co - 0.0688 of leafy vegetables l PART E: TOTAL DOSE FROM ALL EXPOSURE PATlWAY l The total dose from all exposure pathways assumed to be present at the maximum receptor location can be found by simply adding the individual pathway doses l calculated above. Since all the calculations above assumed a unit activity release from the plant vent stack, the combined dose can be stated as dose factor per unit activity released. This then demonstrates the development of the Seabrook ODCM Method I dose factors for gaseous release of particulates from the vent stack. J ( Inhalation dose (Part A) 0.00184 mrem /yr per Ci I Ground plane dose (Part B) 0.658 arem/yr per Ci Ingestion dose total (Part D) 0.449 mrem /yr per Ci Total dose all pathways 1.11 mres/yr per Ci (critical organ is GI-LLI of an adult for Mn-54) i A-19 ODCM Rev. 16 APPENDIX B O CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND TAKEN FROM 10 CFR 20.1-20.602, APPENDIX B O 1 \ 1 1 O l B-1 ODCM Rev. 16 - O APPEN0lx B TO (( 20.1-20.602--CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND (See footnotes at end of Appendut B) r Isotope

Table i Table 11 i Element (atomic number) Col.1--Air M 2- Col 1- As Col. 2-WM (pCi/mt) NN (p mi)

Actnum (89) Ac 227 S 2 x 10-" 6 x 10-* 8 x 10"* 2 x 10-* I 3 x 10-88 9 x 10-8 9 x 10- u 3 x 10" Ac 228 S 8 x 10-8 3 x 10-8 3 x 10" 9 x 10-* I 2 x 10-8 3 x 10-s 6 x 10-" 9 x 10-s Amencium (95) Am 241 S 6 x10-u 1 x 10*

2 x 10. u 4 xjo-.

I 1 x 10-" 8 x 10-* 4 x 10-$8 3 x 10" Am 242m S 6x10ns gxio-* 2x10-u 4 x 10-* I 3 x 10-" 3 x 10-8 9 x 10* *8 9x10" Am 242 S 4 x10-8 4 x 10-s 1 x 10-' 1 x 10" l 5 x 10-8 4 x 10-8 2 x 10-' 1 x 10" Am 243 S 6 x 10- 58 1 x 10" 2 x10-u 4 x 10-* 1 1 x 10"' 8 x 10-4 4 x 10"' 3 x 10*

Am 244 S 4 x 10-* 1 x 10" 1 x 10-' 5 x 10-8 I 2 x10*

1 x10-8 8 x10-' 5 x 10-8 Aremony Sb t ** S 2 x 10-' 8 x10-* 6 x 10-' 3 x 10-8 1 1 x10-' 8x10" 5 x 10*' 3 x 10*

Sb 124 S 2 x10-' 7x10" 5 x10-' 2 x10" i 2x10" 7 x10" 7 x 10-" 2 x 10*

Sb 125 S 5 x 10-' 3 x 10-8 2 x10-* 1 x 10" l 3 x 10*

3 x 10-8 9 x10-" 1 x10" Argon (18) A 37 Sub8 6 x10-s 1 x10**

A 41 Sub 2 x10** 4 x10-8 Arsenc (33) As 73 S 2 x 10** 1 x10-8 7 x 't.0-8 5x10

I 4 x10" 1 x10-8 1 x 10-* 5 x 10-*

As 74 S 3 x 10-' 2 x10-3 gxto-* 5x 10-s 1 1x10" 2 x10-8 4 x10-' 5 x10-s , As 76 S 1 x10-' 6 x 10** 4 x10-8 2 x 10-' i 1 x10-8 6 x10" 3 x10-' 2x10" As 77 S 5 x 10-' 2x10-8 2 x10-8 8 x10-8 1 4 x10-' 2x10-8 1 x10-8 8 x 10-s Astatene (85) At 211 S 7 x to-* 5 x 10-* 2x10-" 2 x 10-* I 3 x10** 2x10-8 1 x10-' 7x10-s Barium (56) Ba 131 S 1x10** 5 x10-a 4x1r* 2x10" l 4 x 10-' 5 x 10'8 1 x10-8 2 x 10-* Ba 140 S 1 x to" 8 x10-* 4 x10-* 3 x 10*

1 4 x10-* 7 x10-4 1 x10** 2x10-8 i Berkelium (97) Bk 249 S 9 x 10-" 2 x to-8 3 x10"8 6x10" i 1 x 10-' 2 x 10-' 4 x 10-' 6 x10*

Ok 250 S 1 x 10" 6 x1g-a 5 x 10-' 2 x 10*

1 1 x10** 6 x10-8 4 x 10-

2 x 10-*

Berytisum (4) Be 7 S 6 x 10-* 5 x 10-8 2 x 10-' 2 x to" j 1 1 x 10-* 5 x 10-8 4 x 10-* 2 x 10-8 j Besmuth (83) Bi 206 S 2 x 10-' 1 x 10-8 6 x 10-* 4 x 10- * ! I 1 x 10" 1 x 10-8 5 x 10" 4 x 10" Bi207 S 2x10" 2 x 10-8 6 x10-' 6 x 10-* 1 1 x 10-8 2 x 10-8 5 x 10- " 6 x 10" Bi210 S 6 x 10-

1 x 10-8 2 x 10- " 4 x 10" 1

O' B-2 CDCM Rev. 16 i Nuciarr Rsskttry Commiszlan Pt. 20 [f 20.1-20.602], App. B APPENOlX B TO (( 20.1-20.602--CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND--Continued + (See footnotes at end of Appenda 8) Isotope

Table 1 Table il Eternent (atomic numbed Col 2- Cd.2-Col.1 4 W gi%

(gCi/m0 g Ci m0 (pCumo ya;er i 6 x 10*

1 x 10" 2 x 10* " 4 x 10" Bi 212 S 1 x 10" 1 x 10 *

3 x 10" 4 x 10" 1 2 x 10- 8 1 x 10-' 7 x 10-' 4 x 10" Storrune (35) Br82 S 1 x 10" 8 x 10* 8 4 x to" 3 x 10" i 2 x 10" 1 x 10* a 6 x 10" 4 x 10-8 Cadmium (48) Cd 109 S 5 x 10-

5 x to-8 2 x 10" 2 x 10" l 7 x 10*

5 x 10-s 3 x 10" 2 x 10" Cd 115m S 4 x 10" 7 x 10-> 1 x 10" 3 x 10" 8 4 x 10*

7x10" 1 x 10" 3 x 10" Cd 115 S 2x 10" 1 x 10-8 8 x 10" 3x10" i 2 x 10" 1 x 10-8 6 x 10" 4 x 10" Calcium (20) - Ca 45 S 3 x 10* 8 3 x to" 1 x 10" 9 x 10" i 1 x 10-' 5 x 10-8 4 x 10*

2 x 10" Ca 47 $ 2x 10" 1 x 10-8 6 x 10" 5 x 10" 1 2 x 10*

1 x 10-8 6 x 10" 3 x10" Califamum (98) Cf 249 S 2 x 10-" 1xto" 5 x 10* " 4 x to" I 1x10*" 7x 10** 3 x 10-u 2 x 10" 0 250 S 5 x 10-'8 4 x 10" 2x10"8 1 x 10" 1 1 x 10-" 7 x 10 *

3 x 10* " 3 x 10*

O 251 S 2x10"8 1 x 10" 6 x 10*" 4 x 10-*

1 1 x 10-" 8 x10" 3 x 10*" 3x10" 0 252 S 6 x 10-" 2x10" 2 x 10"8 7x10" l 3 x10*" 2 x 10*

1 x 10* " 7x10" Cf 253 S 8 x 10* ** 4 x 10-8 3 x10-" 1 x 10-*

I 8 x10-" 4 x 10*: 3 x 10* " 1 x10" Q 254 S 5x10"8 4 x10** 2 x10"* 1 x 10" [ l 5 x10"8 4 x 10** 2 x10"8 1 x 10-' (* Carbon (6) C 14 S 4 x 10-8 2 x10-8 1 x 10" 8 x10" (CO ) S44 5 x 10-* 1 x to" Conum (58) Ce 141 S 4 x 10-' 3 x 10-8 2 x 10-e gxion i 2 x 10-' 3 x10-s 5 x 10" 9 x10" Ce 143 S 3 x 10-' 1 x10** 9 x 10*

4x10" l 2x10" 1 x10-s 7 x io-o 4 xto-Co 144 S 1 x 10*

3 x10" 3 x 10* " 1 x 10-8 8 6x10" 3 x10" 2 x 10*

1 x 10-8 Ceesurn (55) Cs 131 S 1 x10-8 7 x to" 4 x 10" 2 x 10-8 1 3 x10** 3 x 10-8 1 x 10" 9 x 10*

Cs 134m S 4 x10" 2 x10" 1 x10" 6 x10" l 6 x10-8 3 x10-s 2 x 10*' 1 x10-8 Cs 134 S 4 x10-8 3 x10" 1x 10" 9 x 10-8 8 1 x10-a 1x10-s 4 x to-

4 x10' Cs 135 S 5x 10*' 3 x1g-s 2 x 10-8 1x10" l 9x10-8 7 x10*

3 x 10*

2x10" Cs t36 S 4 x 10-' 2x10-8 1 x10" 9 x 10-8 1 2x10" 2x10-s 6 x 10*

6 x10-8 Cs 137 S 6x10-8 4 x10" 2 x 10-' 2x10-8 8 1 x10-e 1x10-s 5 x 10-" 4 x10-8 CNortne (17) Q 36 S 4 x10-' 2x10-8 1 x 10-* 8x10" 1 2x10-* 2 x10* 8 8 x 10-" 6x10-8 0 38 S 3 x10** 1 x 10" 9 x 10-* 4 x 10" 1 2x10-8 1 x10-8 7x 10" 4 x 10-8 Qwomium (24) Cr 51 S 1 x10** 5 x 10* 8 4 x 10" 2x10" 1 2x10-8 5 x 10-8 8 x 10.e 2 x 10" Cotwt (27) Co57 S 3x to-* 2 x 10* 8 1 x 10" 5 x 10" l 2 x 10-' 1 x 10-8 6 x 10" 4x10" Co S8m S 2x 10-8 8 x 10" 6x 10" 3 x 10-8 8 9 x 10*

6 x 10-8 3 x 10* ' 2 x 10" Co S8 S 8 x 10" 4 x 10-8 3 x 10" 1x10" i 5 x 10" 3 x 10* 8 2 x 10*

9 x 10-8 Co 60 S 3 x 10-' 1 x 10-8 1 x 10*

5 x 10" l 9 x 10-8 1 x 10-8 3 x 40-

3 x 10" Copper (29) Cu 64 S 2x to-* 1 x 10" 7 x 10" 3 x 10"

( l 1 x 10-8 6 x 10-8 4 x 10" 2 x 10" ( Cunum (96) Cm 242.. S 1 x 10* " 7 x 10" 4 x 10"8 2 x 10" B-3 ODCM Rev. 16 Pt. 20 [ f 20.1-20.602], App. B 10 CFR Ch. I (1-1-93 Edition) l 1 APPENOlX B TO sf 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued (See teotnotes at end of Appendix B] tsotope

Tabke 1 Table 11 Element (atome number) g, ,4 Col 2- g , ,_4, Cot 2-4W (gC m0 4Ci/N ( C /ml)

I 2x10-" 7 x 10" 6 x 10- " 2 x 10" Cm 243 S 6 x 10"8 1 x 10-* ~2 x 10-" 5 x 10-8 1 1 x 10-" 7 x 10-

3 x 10- " 2 x 10" Cm 244 S 9 x 10* " 2 x 10" 3 x 10* " 7 x 10*

1 1x10-" 8 x 10" 3 x 10- '8 3 x 10" Cm 245 S 5x10-" 1 x 10" 2 x 10"8 4 x 10-*

1 1 x 10-" 8 x 10" 4 x 10-" 3 x 10-8 Cm 246 S 5 x10- u 1 x 10" 2 x 10- " 4 x 10-* I 1 x 10* " 8 x 10-* 4 x 10* " 3 x 10*

Cm 247 S 5x10-u 1 x 10" 2 x 10-" 4 x 10" i 1 x 10-" 6 x 10" 4 x 10* " 2 x 10" Cm 248 S 6 x 10"8 1 x 10" 2 x 10* " 4 x 10-'

I 1 x 10* " 4 x 10-* 4 x 10* " 1 x 10-* Cm 249 S 1 x10" 6 x 10-8 4 x 10" 2 x 10-8 1 1 x10-8 6 x 10- 4 x 10" 2 x10-s Dysprosasn (66) Dy 165 S 3 x10" 1 x 10-8 9 x 10" 4 x 10-* i 2 x 10-* 1 x 10-8 7 x 10" 4 x 10" Oy 166 S 2x10" 1 x 10-8 8 x 10-' 4 x 10-* I 2 x10" 1 x 10*

7 x 10" 4 x 10" Einstemnium (99) Es 253 S 6x10-" 7xto" 3 x 10- " 2x10" l 6 x 10* " 7 x 10" 2 x 10-" 2x10" Es 254rp S 5x10" 5 x 10-* 2 x 10-" 2 x 10" l 6 x10" 5x10" 2 x 10-" 2 x 10-8 Es 254 S 2x10 u 4x10" 6x10 " 1 x 10-

1 1 x 10*" 4 x10-4 4 x 10"8 1 x 10-8 Es 255 S 5 x10-" 8 x 10" 2 x 10* " 3 x 10-*

I 4 x10*

8 x 10"* 1 x 10-" 3x10" Ertnum ($3) Er 169 S 6 x to-' 3 x 10*

2 x 10-* 9 x 10*

I 4 x10-' 3 x to-8 1 x 10" 9 x10*

Er 171 S 7 x10-' 3 x 10* 8 2 x10" 1 x to" l 6x10-' 3 x10" 2 x to-* 1 x to" Etropsam (63) Eu 152 S 4 x 10-' 2 x10-8 1 x10" 6 x to" (T/2=9.2 tys)_ i 3 x10-' 2 x10-s 1x10-e 6 x10.s Eu 1o S 1 x 10-8 2 x 10-8 4 x 10-" 8 x to-*

(T/2=13 yrs) 1 2 x 10-' 2 x 10-8 6 x 10-" 8 x10-5 Eu 154 S 4 x 10-8 6 x to" 1 x 10-" 2 x 10-s i 7 x10-' 6x10" 2 x 10-" 2 x10" Eu 155 S 9 x10-8 6 x10-8 3 x 10" 2 x 10-* I 7x10-a 6 x10" 3 x10" 2 x 10-* Fermium (100) Fm 254 S 6 x10-* 4 x 10-* 2 x10-' 1xto" l 7 x10** 4 x 10-8 2 x10-' 1 x 10-* Fm 255 S 2 x10-e 3xio-a 6 x 10-" 3 x 10-8 1 1 x10** 1 x10-s 4 x to-w 3 xio-s Fm 256 S 3 x10" 3 x 10-8 1 x10* " 9 x 10-' l 2x10-8 3 x10-8 6 x 10-" 9 x10" Fluonne (9) F 18 S 5 x10-* 2x10-8 2 x 10*' 8 x 10-* I 3x10-8 1 x 10-8 9 x 10-8 5 x to-* Gadolinium (64) Gd 153 S 2 x10-' 6 x 10" 8 8 x 10" 2x10-* I 9 x10-s 6 x 10-8 3 x 10" 2x10-* Gd 159 $ 5 x10-' 2 x10-8 2x10" 8 x 10-8 4 4 x10-? 2 x 10-8 1 x10-e a x io-s Gataan (31) Ga 72 S 2 x10-' 1 x 10-

8 x to-' 4 x M-

1 2 x10-' 1 x 10-a 6 x 10" 4 x 10-8 Germaruum (32) Ge 71 S 1 x 10" 5 x 10-8 4 x 10" 2x10 s i 6 x10-* 5 x 10- 8 2 x 10-' 2 x 10- 8 i i Gold (79) Au 196 S ' 1 x10-* 5 x 10-8 4 x 10" 2 x 10" j 1 6 x10" 4 x 10*

2 x 10" 1x10" j Au 198 S 3x10" 2 x 10" 1 x 10-

5 x 10-* i i 2 x 10" 1 x 10" 8 x 10" 5x10" l Au 199.- S 1 x 10-* 5 x 10-8 4xto" 2 x 10" j l 8 x10" 4 x 10" 3 x to" 2 x 10" l Hafrwurn (72) Hf181 $ 4 x 10-8 2 x 10" 1 x to-* 7 x 10" !

l 7 x10" 2 x 10" 3 x 10" 7 x 10" G Ho6mium (67) . Ho 166 S 2 x 10-' 9 x 10" 7x1,0" 3 x 10" l B-4 ODCM Rev. 16 l Nuciar Rcgulatary Csmmissinn Pt. 20 [(( 20.1-20.602), App. B APPENDIX 8 TO {$ 20.1-20.602--CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL p BACKGROUNO-Continued \ (See footnotes at end of Appendat B] Isotope ' Tabee i Table it Element (atomic numoet) g% Col. 2- g,m Col. 2-4GmQ [,g) baGmQ mQ l 2 x 10* ' 9 x 10*

6 x 10*

3 x 10-

Hydrogen (1) H3 S 5 x 10-* 1 x 10" 2 x 10" 3 x 10- 8 3 5 x 10" 1 x 10" 2 x 10- ' 3x40" Sub 2 x 10*

4 x 10" i indium (49) in 113m S 8 x 10** 4 x 10* 8 3 x 10-' 1x10" !

l 7 x 10*

4 x 10- 8 2 x 10" 1 x 10* 8 in 114m S 1 x 10" 5 x10" 4 x 10" 2 x 10" I 2 x 10-8 5x10** 7 x 10* " 2 x 10*

In 115m S 2 x to-* 1 x 10" 8 x to" 4 x to" 1 2 x 10-* 1 x 10*

6 x 10*

4 x 10-

In 115 $ 2 x 10-' 3 x 10-s g x ion g xion i 3 x 10-8 3 x 10-s 1 x 10-* 9 x 10-

todine 453) I125 S $ x 10" 4 x 10-* 8 x 10* " 2xt0" 1 2 x 10*' 6 x 10" ,

6 x 10" 2 x 10" 1126 S 8 x10" 5 x 10" 9 x 10-" 3 x 10*' 1 3 x 10*' 3 x 10*

1 x 10*

9 x 10" 1129 S 2 x 10** 1 x 10-* 2 x 10* " 6 x 10-*

I 7 x 10-8 6 x 10-8 2 x 10*

2 x 10" (131 S 9 x10" 6 x10" 1 x 10*

3 x 10" 1 3 x 10-8 2 x 10-8 1 x 10" 6 x 10*

1132 S 2 x 10-' 2 x 10-8 3 x 10" 8 x 10" j i 9 x 10*' 5 x 10*

3 x 10*

2 x 10" 1133 S 3 x 10-* 2 x 10-* 4 x 10* " 1 x 10**

I 2 x10" 1 x10-s 7 x 10" 4 x 10" I134 S 5 x 10*' 4 x10-s 6x10" 2x10" 1 3 x10-* 2 x 10* 8 1 x10" 6 x 10*

1135 S 1 x 10-' 7 x10" 1 x 10-* 4 x 10*

O iridium (77) tr190 1

l 4 x 10-' 1 x 10-* 4 x 10-' 2 x10" 6 x 10-8 5 x 10-s 1 x 10" 4xto" 1 x 10" 7 x 10" 2 x 10" 2x10" Ir 192 S 1x10" 1 x10-s 4 x 10" 4 x 10" 1 3 x 10** 1 x 10*

9 x 10- " 4 x 10-

Ir 194 S 2x 10" 1 x10's ex3on 3 x ton 1 2x 10" 9 x 10-* 5x10" 3 x10-s iron (26) Fe 55 S 9 x 10-' 2x 10-8 3 x 10" 8 x 10" 1 1 x 10-* 7 x 10" 3 x10" 2x10 s Fe 59, S 1 x10" 2x10-s 5 x 10*

6 x10" l 5 x 10-* 2x10-8 2x10-* 5 x 10-8 Krypton (m Kr 85m Sub 6 x 10-* 1 x 10" Kr 84 SW 1x10-* 3 x10" Kr 87 SW 1 x10-8 2x10" Kr88 Sub 1 x 10-8 2x10-e Langhanum (57) La 140 S 2x10-' 7 x to" 5 x10" 2 x to-s I 1 x 10-' 7 x10*

4 x10-* 2x10-s Lead (60 Pb 203 S 3 x 10-* 1 x to- 9 x10" 4x10" 1 2 x10** 1 x 10-8 6x 10" 4 x10" Pb 210 S 1 x 10-" 4 x 10-* 4 x 10-'8 1x10" i 2 x10-" 5x10-s eggons 2 x 10-*

Pb 219 S 2 x t0-8 6 x10-* 6 x 10*" 2 x 10-* I 2 x10-* 8 x 10*

7x10-# 2 x 10-*

LaAshm (71) Lu 177 S 6 x 10-' 3 x to-8 2 x 10"* 1x10" 1 5 x10" 3 x10-8 2 x 10 1 x10" : Manganees (25) _ Mn 52 S 2 x10" 1 x 10- 7x3eo 3 x yon i 1 x10" 9 x 10** 5 x10" 3 x 10** Mn54 S 4 x 10" 4 x 10*

1 x 101 1 x 10" l 4 x10" 3 x10-s yxgo e y x to" Mn56 S 8x10" 4 x 10-8 3xM-* 1 x 10" l 5 x10" 3 x 10- 8 2 x10" 1 x 10" Mercury (80) Hg 197m .S 7xto" 6 x 10-8 3 x 10" 2 x 10" 1 8 x 10*' 5 x 10-8 3 x 10" 2 x 10" Hg 197 S 1 x 10** 9 x10" 4 x 10" 3 x 10" 1 3 x10*

1 x 10" 9 x 10" 5 x 10"

$ 7 x 10" 5xt0" 2x10" 2 x 10*

D Hg 203 i 1 x 10" 3 x 10-8 4 x 10" 1 x 10" B-5 ODCM Rev. 16 j l

i Pt. 20 [{ 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Edition) APPENotX B TO fl 20.1-20.602-CONCENTRATIONS IN AsR AND WATER ABOVE NATURAL BACKGROUND-COfitif)Ued (See footnotes at end of Appendoi 0] isotope

Table i Tatne n Element (atome number) g% Col. 2- Col. 1 -4 Cot 2--

(pCi/ml) hk (pCi/mt) $*y' Molyt>denum (42) Mo 99. S 7 x 10" 5 x 10-8 3 x 10" 2 x 10" l 2x10-8 1 x 10- 8 7 x 10-' 4 x 10" Neodymsum (60) Nd 144 S 8 x 10-" 2 x 10- 8 3 x 10-'8 7 x 10" l t 3 x 10-" 2 x 10* 8 1 x 10-" 8 x 10" Nd 147 $ 4 x 10" 2 x to-* 1 x 10" 6 x to" I 2 x 10-' 2 x 10-: 8 x 10" 6 x 10" Nd 149 S 2 x 10-* 8 x 10" -6 x 10" 3 x 10" i 1 x 10-* 8 x 10. 5 x 10" 3 x 10" Neptunsum (93) No 237 S 4 x 10"' 9 x 10" 1 x t0-" 3 x 10-* 1 1 x 10"* 9 x 10" 4 x 10"8 3 x 10-* Np 239 S 8 x 10-8 4 x 10-: 3 x t o" 1 x to" l 7 x10" 4 x10 s 2 x 10" 1 x 10" Nidel (28) Ni 59 S S x to" 6 x 10- 8 2 x 10" 2 x to" l 8 x 10" 6 x 10" 3 x 10" 2 x 10- 8 Ni 63 S 6 x10*

8 x 10" 2 x 10" 3 x 10" 1 3 x 10" 2 x 10* 8 1 x 10" 7 x 10" Ni 65 S 9 x10" 4 x 10" 3 x 10" 1 x 10" l 5 x 10 ' 3 x10" 2 x 10" 1 x 10" I

Niobsum (Columbaum) (41) Nb 93m S 1 x 10-' 1 x to" 4 x 10" 4 x 10" l 1 2 x 10-' 1 x 10-8 5 x 10-* 4 x 10" NO 95 S 5 x10-' 3 x 10-8 2 x 10-* 1 x 10*

1 1 x 10" 3 x 10-8 3 x 10 ' 1 x 10" l

Nbg7 S 6 x 10-* 3 x 10-s 2 x 10" 9 x 10-

l t 5 x10** 3 x 10-8 2 x10" 9 x 10" Osmaam (76) Os 185 S 5x10" 2 x 10-8 2 x10" 7 x 10" i 5 x10-s 2 x 10-8 2 x10" 7 x 10" Os 191m S 2x10" 7 x 10-8 6 x 10" 3xto" l 9 x 10-* 7 x 10-8 3 x10" 2 x 10" Os 191 S 1 x 10-* 5x10" 4 x 10" 2 x10" l 4 x 10-8 5 x10- 1 x10" 2 x 10" Os 193 $ 4 x10" 2 x 10* 8 1 x 10" 6 x 10" l 3 x10" 2x 10-8 9 x10" 5 x 10" l Palladium (46) Pd 103 S 1 x 10-8 1 x 10-' 5xto

3 x 10"

! l 7x10" 8 x10" 3 x 10-' 3 x 10" l Pd 109 S 6 x10" 3 x 10-8 2x 10" 9 x 10*

I 8 4 x 10-' 2 x 10-8 1 x 10- 8 7 x 10-*

Phosphorus (15) P 32 S 7 x 10-* 5 x 10-* 2 x t o-' 2 x 10" l 8x10-8 7 x 10*

3 x10" 2 x 10-8 Plannum (78) Pt 191 S 8 x 10-' 4 x 10-8 3 x10" 1 x 10" l 6 x10-' 3 x 10-8 2 x10-s ixton Pt 193m S 7 x10** 3 x 10-8 2 x10" 1x1g-s 1 5 x 10-* 3 x10-8 2x10" 1x178 Pt 193 $ 1 x 10-* 3 x10-8 4 x 10-8 9 x 10-

I 3 x 10-' 5 x 10-8 1 x 10-8 2 x 10" Pt 197m S 6 x10** 3 x 10-8 2 x 10" 1 x 10-8 1 5x10-8 3 x10-8 2 x 10" 9 ).10-

Pt 197 $ 8 x10-' 4 x10- 3 x 10" 1 x 10" l 6 x10-' 3 x10-8 2 x10" 1 x 10" Plutonaan (94) Pu 238 S 2 x10-u i x1on 7 x t o- u g x io-a 1 3 x 10-" 8 x10" 1x10"8 'JX10**

Pu 239 S 2 x10-'8 1 x 10-* 6 x 10- " 5 x 10-8 f 1 4 x 10-" 8 x 10-8 1 x 10-" 3 x 10" l Pu 240 S 2 x 10*" 1 x 10-* 6 x 10 " 5 x 10** I 4 x 10-H 8 x 10-* 1 x 10"' 3 x 10" Pu 241 - S C x10* " 7 x 10-s 3 x 10 " 2 x 10" t 4 x 10*

4 x 10-8 1 x 10-' 1 x10" Pv 242. S 2 x 10-'8 1x10" 6 x 10"* 5 x 10*

I 4 x 10- " 9 x 10-* 1 x 10"* 3 x 10 8 Pu 243 $ 2 x 10-* 1 x 10-8 6 x 10-

3 x 10" 1 2 x 10-* 1 x 10- 8 8 x 10-

3 x 10-

Pu 244_ S 2 x 10-" 1 x 10" 6 x 10"* l 4 x 10 *

i 3 x 10-" 3 x 10-

1 x 10-" - 1x10" Po 210... ... S 5 x 10- " 2 x 10" 2 x 10- " 7 x 10" Polonsum (84) _

1 2 x 10* " 8 x 10" 7 x 10- r 3 x 10" B-6 ODCM Rev. 16 l _a Nuclear Regulatory Commission Pt. 20 [@@ 20.1-20.602), App. 8 APPENDtX B TO (( 20.1-20.602-CONCENTRATIONS IN AIR ANO WATER ABOVE NATURAL , BACKGROUND--Continued (See footnotes at end of Appendex 8] 150 tope

7atHe i Table it Ewment (atorme number) Cd t w Col 2- g, im Col 2-04Cumf)

[Ci/ (SCa/ms) [*j'y ( Potassum (19)- K42 S 2 x 10'

9 x 10" 1 x 10" 3 x 10' i 1 x 10 * ' 6 x 10*

d x to" 2 x 10" Praseodymouro (59) Pr 142 S 2 x 10* ' 9 x 10" 7 x 10" 3 x 10" I 2 x 10* 8 9 x 10' 5 x to" 3 x 10" Pr 143 S 3 x 10* ' 1 x 10' 1 x to" 5 x 10" l 2 x 10 * ' 1 x 10* 8 6 x 10*' 5 x 10" Promettwum (61L Pm 147 S 6 x 10" 6 x 10" 2 x 10" 2 x 10" 1 1 x 10* ' 6 x 10" 3 x 10" 2 x 10" Pnt149 5 3 x 10* ' 1 x 10 *

1 x 10*

4 x 10 *

1 2 x 10* ' 1 x 10* 8 8x10** 4 x 10*

Protoactenium (91) - Pa 230 S 2 x 10*' 7 x 10' 6 x 10"' 2 x 10" 1 8 x 10"' 7xto" 3 x 10"' 2 x 10" Pa 231- S 1 x 10* *8 3 x t0*

4 x 10* " 9 x 10* '

1 1 x to* 8 x 10" 4 x it0"8 2 x 10" Pa 233 S 6 x 10" 4 x 10" 2 x 10" 1 x 10" 1 2 x 10* ' 3 x 10*

6 x 10" 1 x 10" Radium (88) Ra 223 .. S 2 x 10" 2 x 10" 6 x 1.0 * " 7 x 10' I 2 x 10"' 1 x 10" 8 x 10"1 4 x 10 *

Ra 224 S 5 x 10" 7 x 10" 2 x 10*

2 x 10" l 7 x 10*

2 x 10" 2 x 1C -" 5 x 10*

Ra 226 S 3 x 10"' 4 x 10" 3 x 10 * " 3 x to" I 5 x 10"' 9 x 10" 2 x 10"2 3 x 10" Ra 228 S 7 x 10"' 8 x 10" 2 x 10"2 3x to" 1 4 x 10* " 7 x 10" 1 x 10* " 3 x to" Redon (86) Ari220 S 3 x 10" 1 x 10'"

Rn 222 8 3 x 10" 3 x 10" IO Rheruum (75) Re 183 Re 186 S 1 S 3 x 10*

2 x 10* '

6 x10" 2 x 10" 8 x 10" 3 x 10-s 9 x 10" 5x10" 2 x 10" 6 x 10" 3 x 10** 9 x 10" 1 2x10" 1 x 10-s 8 x 10"' 5 x 10" Re 187 S 9 x 10*

7 x 10- 3 x 10" 3 x 10*

I 5 x10" 4 x 10* ' 2 x 10*

2 x 10*

Re 188. S 4 x 10-' 2 x 10* 8 1 x 10** 6 x 10* *

. I 2 x 10* ' 9 x 10*

6 x 10*

3 x 10*

Rhodium (45) _ Rh 103m S 8 x 10*

4 x 10*

3 x 10** 1 x 10" l 6 x10*

3 x 10" 2 x 10** 1 x 10" Rh 105 S 8 x 10" 4 x 10*

3 x 10-8 1 x 10" i 3 x 10-s 2 x 10" '1 x 10" Rdxhum (37) At> 86 S 5 x10" 3 x 10". 2 x to-8 1 x 10" 7 x 10*

I 7 x 10*

7 x10" 2 x 10** 2 x to-8 '

Rb 87 S 5 x 10*' 3 x 10-8 2 x 10** 1 x 10*

I 7 x10*

5 x10" 2 x 10*

2 x 10" Rutheruum (44) N 97 S 2 x10*

1 x 10-8 8x10 e 4 xgo-.

I 2 x 10*

1 x 10-3 6 x 10*

3 x 10" Ru 103 S 5 x10" 2 x10" 2 x10*

8 x 10*

I 8 x10*

2 x 10*

3x10" 8 x 10*

Ru 105 S 7 x10*' 3 x10" 2 x 10*

1x10" )

1 5 x10* ' 3 x10" 2 x to" it x 10*

Ru 106 S 8x10" 4 x 10" 3 x 10** Y x 10-

I 6 x10" 3 x 10" 2 x 10* " 1 x 10" Samanum (62). Sm 147 S 7 x 10*" 2 x 10" 2 x 10"' 6 x to-*

I 3 x 10* " 2 x10" 9 x 10*" 7 x 10*

Sm 151 S 6x 10" 1 x 10*

2 x 10" 4 < 10" i 1 x10" 1 x 10** 5 x 10" 4 x 10" Srn 153 S 5 x 10" 2 x 10" 2 x 10" 8 x 10" l 4 x 10* ' 2 x 10~ 8 1 x 10-e 8 x 10*

Scandium (21) Sc 46 $ 2x10" 1x10 8 x 10" 4n10**

I 2 x 10" 1 x to" 8 x to"* 4 x 10" Sc 47 S 6 x 10* ' 3 x 10* 8 2 x 10*

9 x 10*

I 5 x 10" 3 x 10*

2 x 10" 9 x 10" Sc 48 S 2 x 10* ' 8 x to" 6 x 10" 3 x 10" t 1 x 10 * ' 8 x 10" 5 x 10 * ' 3 x 10*

Seterwum 34) . Se 75 - S 1 x 10*

9 x 10* 8 4 x 10" 3 x 10" i 1 x 10" . 8 x 10" 4 x 10" 3 x 10" B-7 ODCM Rev. 16 l

I ] Pt. 20 [@f 20.1-20.602], App. B 10 CFR Cil. I (1-1-93 Editisn) APPENOlX B TO fl 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATUAAL BACKGROUND-Continued (See footnotes at end of Appenen B] isotope ' Tatse i Tatse u Emment (atome numt*) g% Col. 2- 3,w Cot 2-(MOM) ( mi) (ACa/ml) af Sa31 S 6 x 10*

3 x 10" 2 x 10 * ' 9 x 10" Sascon (14) 1 1 x 10** 6 x 10*

3 x t0" 2 x 10*

Ag 105 S 6x10" 3 x 10- s 2 x 10" 1x10" Selver (47) .

l 8 x 10*

3 x 10*

3 x 10*

l 1 x 10*

Ag 110m - S 2 x 10 * ' 9 x 10' 7 x 10" l 3 x 10" I 1 x to'* 9 x 10" 3 x 10*

3 x 10' Ag 111 S 3 x 10" 1 x 10- 8 1 x 10" 4 x 10" l 2 x 10* ' 1 x 10* 8 8 x 10 * ' 4 x 10*

Na 22 S 2 x 10" 1 x 10" 6 x 10" 4 x 10" Sodurn (11) 3 x 10" l 9 x 10" 9 x 10" 3 x 10* "

Na 24_ S 1 x 10*

6 x 10- 8 4 x 10*

2 x 10*

1 1 x 10* ' 8 x 10" 5 x 10" 3 x 10" Sr 85m S 4 x 10' 2 x 10" 1 x 10** 7xto" Stronnum (38) __

1 3 x 10* 8 2 x 10" 1 x 10 *

7 x 10- 8 Sr 85 S 2 x 10" 3 x 10*

8 x 10" 1 x 10" i 1x10" 5 x 10" 4 x 10" 2 x 10" Sr 89 S 3 x 10*

3 x 10* ' 3 x 10*

3 x 10**

I 4 x 10*

8 x 10" 1 x 10" 3 x 10*

Sr90 - S 1 x10" 1 x 10" 3 x 10* " 3 x 10" l 5 x 10" 1 x 10- 8 2 x 10"* 4 x 10" Sr 91 S 4 x 10* ' 2 x 10*

2 x 10*

7 x 10- 8 I 3 x 10* ' 1 x 10- 3 9 x 10* ' 5 x 10* 8 Sr 92 S 4 x 10" 2 x10" 2 x 10" 7 x 10*

I 3 x10" 2 x 10*

1 x 10" 6 x 10*

S 35 S 3 x 10" 2 x 10- 8 9 x 10" 6 x 10" Suttts (16) 3 x 10" 1 3 x10" 8 x 10" 9 x 10" Ta 182 S 4 x 10*

1 x 10-a 1 x 10" . x 10" Tantalum (73) 1 2 x 10*

1 x 10*

7 x 10*

4 x 10*

Technetium (43) Tc 96m S 8 x10" 4 x 10-' 3 x 10*

1 x 10* 8 1 3x10-s 3 x 10" 1 x 10-* 1 x 10-8 Tc 96 S 6x10" 3 x10* 8 2 x10" 1 x 10*

I 2 x10" 1 x10- 8 8 x 10" 5 x10" TcS7m S 2 x10*

1 x 10-8 8 x 10*

4 x 10" I 2 x 10* 8 5 x 10*

5 x 10* ' 2 x 10*

Tc 97. 5 1 x 10" 5 x 10* 8 4 x 10" 2 x 10- 8 1 3 x 10* 8 2 x 10-8 1 x 10" 8x10" Tc99m S 4 x10" 2 x10" 1 x 10*

6 x 10* 8 8 1 x 10* 8 8 x10-8 5 x 1C-' 3 x10-s Tc 99 S 2 x10*

1 x 10-s 7xto-a 3 x to-a 1 6 x10-s 5 x 10* 8 2 x 10*

2 x 10*

To 125rn S 4 x to" 5 x 10" 1 x 10-* 2xto" Temunum (52) i 1 x 10" 3 x 10" 4 x 10*

1 x 10" Te 127n' S 1 x 10" 2 x 10' 8 5 x 10" 6 x to'*

1 4 x 10*

2 x 10* 8 1 x 10" 5 x10" To 127 S 2 x 10** 6 x 10*

6 x 10" 3 x to" l 9 x10" 5 x 10" 3 x10" 2 x 10*

Te 129m --- S 8 x10" 1 x 10" 3 x 10** 3 x 10*

I 3 x10" 6 x 10" 1 x 10" 2 x 10" Te 129 S 5x10" 2 x 10* 8 2 x 10*' 8x10" ,

t 4 x 10** 2 x 10* 8 1 x 10* ' 8x10" To 131m S 4 x 10" 2 x10" 1 x 10" 6 x 10" ; I 2 x 10" 1 x 10- 8 6 x 10" 4 x 10* * , I Te 132 S 2 x 10" 9 x 10" 7 x 10" 3 x 10" i 1 x 10" 6 x 10" 4 x 10" 2 x 10" Tb 160 : S 1 x to-' 1 x 10" 3 x 10" 4 x 10" Tertzm (65) 1x10 8 1 x 10*

4 x 10" l 3 x 10" TI200 S 3 x 10" 1xto 8 9 x 10" 4 x 10-

Thamum (81) 2xto" 1 1 x 10** 7 x 10'8 4 x 10" Tl201 S 2 x 10-* 9 x 10* 8 7 x 10-* 3xto" l 9 x 10" 5 x t0" 3 x 10" 2 x 10' Tl202 S 8 x 10" 4 x 10' 3 x 10" 1 x 10*

I 2 x 10" 2 x 10* 8 8 x 10*

7 x 10" 3 x 10" 2 x 10" 1 x 10*

6 x 10-'

Ti204.. . . . . .. S 6x 10 " 1 3 x 10-* 2 x 10" 9 x 10*

B-8 ODCM Rev. 16 i

1 l l l Nuclear Regulatory Commission Pt. 20 [@ 20.1-20.602], App. B l l APPENOlX 8 TO (( 20.1-20.602-CONCENTRATIONS IN AIR AND WATER AsovE NATURAL ( BACKGROUNO--Continued [See footnotes at end of Appendu 0] Isotope ' Tab 6e i Table H Element (atorme number) Col 2- Col. 2-Col 1 4 Cot 1--h 4W ( $$) bW (3d$) Thonum (90) .. Th 227 S 3 x to-" 5x10" 1 x to-" 2 x to" i 2 x 10-" 5 x 10" 6 x 10-" 2 x 10" Th 228.. S 9 x 10"8 2xto" 3 x 10"8 7 x 10-* I 6 x 10* " 4x10" 2 x 10"* 1 x 10" Th 230 S 2 x 10"8 5 x 10" 8 x 10* " 2 x 10 8 8 1 x 10-" 9 x 10" 3 x 10"8 3 x 10" Th 231 S 1 x 10** 7 x 10*

5 x 10" 2 x 10" 1 1 x 10-8 7 x 10- 8 4 x 10" 2 x 10" Th 232 S 3 x 10* " 5 x 10-

1 x 10* " 2 x 10-

1 3 x 10* " 1 x 10" 1 x 10"8 4 x 10" Th natural S 6: 10- " 6 x 10-

2 x 10* " 2 x 10" 1 6 x 10-" 6 x 10" 2 x 10 * " 2 x 10" Th 234 S 6 x 10-* 5 x 10-* 2 x 10-* 2 x 10-*

1 3 x 10-* 5 x10-* 1 x 10" 2 x 10-

Thuhum (69) Tm 170 S 4 x to" 1 x10" 1 x 10" 5 x to" 1 3 x 10*

1 x 10-8 1 x 10" 5 x 10" Tm 171 S 1 x 10* ' 1 x 10-' 4 x 10** 5 x 10*

I 2 x 10-' 1 x 10-8 8 x 10-' 5 x 10*

Tin (50) Sn 113 S 4 x to-* 2x to-8 1 x 10" 9 x 10-8 1 5 x 10-' 2x10-8 2 x 10" ex10" Sn 125 S 1 x10" 5 x10*

4 x 10" 3 x 10*

1 3 x10-* W10" 3 x 10" 2 x 10" Tungsten (Woutam)(74) W 181 S 2 x 10-8 1x10-8 8 x 10" 4 x 10-*

1 1 x10" 1 x10-s 4 x ton 3 x io-. W 185 S 8x10" 4x10-8 3 x 10" 1 x 10" A i 1 x10" 3 x10-8 4 x 10" 1 x 10*

I W 187 S 4 x 10" 2x10-s 2x 10" 7 x 10" '

\ l 3 x10" 2 x 10-8 1 x10" 6 x 10" Urannan (oSi . . - . U 230 S 3 x10-" 1x10" 1 x 10-" 5 x to-* 1 1 x10* " 1 x 10-* 4x10"8 5 x 10-* U 239 S 1 x10-" 8 x 10-* 3 x10"8 3 x 10-$ I 3 x 10-" 8 x10*

9 x 10"8 3 x10" U 233 S 5 x 10-" 9 x10** 2 x 10* " 3 x 10-*

1 1 x10*

9x10" 4 x 10"* 3 x 10-6 U 234 S* 6 x10-" 9 x 10-* 2x 10-" 3 x 10-*

1 1 x10-" 9 x10" 4 x 10"8 3 x10" U 235 S* 5x10-" 8 x 10** 2x 10-" 3 x10" i 1 x10-" 8 x 10-* 4 x 10"' 3 x10-5 U 236 S 6 x10-" 1 x10-8 2 x 10-" 3 x 10" 1 1 x10*" 1 x10-8 4 x 10"8 3 x 10-* U 238 S* 7xt0-" 1 x10-8 3 x 10"* 4 x 10-5. I i 1 x10-" 1 x 10-8 5x10 " 4 x 10" U 240 S 2 x10-' 1 x10-s 8 x10" 3 x 10-* 1 2 x10-8 1 x10-8 6 x 10-' 3 x 10-8 Ucatural S* 1 x10*" 1 x10-s 5 x10"8 3 x10" 1 1 x 10-" 1x10-8 5x10"8 3 x 10-* Vansdum (23) V 48 S 2 x10*' 9x10** 6 x 10-' 3 x to-* I 6 x10-e 8 x10-* 2x 10" 3 x 10** Xenon (54) Xe 131m Sub 2 x10-* 4 x 10" Xe 133 Sub 1 x13-* 3 x10" Xe 133m Sub 1 x 10-8 3 x 10-' Xe 135 Sub 4 x 10-8 1 x 10" . Ytteddum (70) Yb 175 S 7 x 10-8 3 x 10-* 2 x 10" 1x10" l

v 10"

. 3 x 10.s 2 x 10" 1 x 10" Yttnum (39) ~ Y 90.- S 1 x to-' 6 x 10" 4 x to" 2 x to" i 1 x 10*' 6 x 10-* 3 x 10" 2 x 10- 6 Y 91m S 2 x 10-8 1 x 10- 8 8 x 10* ' 3 x 10- 8 8 2 x 10-8 1 x 10" 6 x 10" 3 x 10" Y 91. S 4 x 10" 8x10" 1 x 10" 3 x 10" l 3x10-8 8 x 10" 1 x 10" 3 x 10-8 ~ Y 92. . S 4 x 10" 2 x 10" 1 x 10" 6 x to" j i 3 x 10-' 2x 10-8 1 x 10-* 6 x 10" t Y 93 .. . .. S 2 x 10" 8x10" 6 x 10" 3 x 10" i 1x10" 8 x 10" 5 x 10- * . *1 . x 10" B.9 ODCM Rev. 16 Pt. 20 [9s 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Edition) APPENOtX B TO ff 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOvE NATURAL BACKGROUNO-Continued (See footnotes at end of As, pen &x B3 isotope ' Table i Table n Elernent (atome number) Col. M Col.2- g 3 4, Col. 2-(pCi/mi) (gCumt) ate a,te Inc (30) . - . . Zn 65.. $ 1 x 10" 3 x 10" 4 x 10" 1 x 10" l 6x 10" 5x10" 2 x 10" 2 x 10" 2n 69m S 4 x 10" 2 x 10" 1 x 10" 7 x 10" l 3 x 10* ' 2 x 10*

1 x 10*

6 x 10*

2n 69. S 7 x 10*

5 x 10-8 2 x 10* ' 2 x 10*

I 9 x 10*

5 x 10" 3 x t0" 2 x 10" Zircorwum (40) 2r 93 S 1 x 10*' 2 x 10" 4 x 10" 8 x 10" 1 3 x 10" 2 x 10-8 1 x 10" 8 x 10" 2r 95 S 1 x 10" 2 x 10" 4 x 10" 6 x 10" t 3 x 10*

2 x 10-8 1 x 10*

6 x 10*

2r 97 S 1x10" 5 x 10" 4 x 10" 2 x 10" l 9 x 10*

5 x 10*

3 x 10*

2 x 10*

Any sang 6e radionuchde not ksted above Sub 1 x 10** 3x10" with decay mode c.ther than alpha emsssion or scontaneous Essco and with radioactive haff4fe less than 2 hows.

Any single raeonuclide not listed above 3 x 10" 9 x 10" 1 x 10"' 3 x 10

with decay mode other than alpha emission or spontaneous fission and w'th rahar*ve half 4fe greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Any single radionuclide not ksted 6x tons 4 x 10" 2 x 10* " 3 x 10*

above, which decays by alpha emis-aion or spontaneous Essen.

' Soluble (S); trwr* Na (1). '"Sub" means that values geven are for submersson in a s . a4-4 innnite doud of arborne matenal. 'These redon concentratens are appropriate for protectien trorn rador>222 combned wrth its short4wed daughters. ' AAematively, me value an Table t may be replaced by one-thin $ (%) " working level" (A "wortang level" is derned as any l combmeton of shor14ved rador>222 daughters, polonum-218, lead-214, bismuth-214 and poloniurn 214 in one Eter of air. I without regard to the degree of equihbnum, that wig result in the uitsmate emelsson of 1.3 x10 8 MeV of alpha partcle energy.) ' The Table it weiue may be rata-1 by one-thirtieth (%e) of a "wortting. level" The timit on radon-222 concentrataons en l reeaicted areas may be based on an annual average.

For sciuble madures of U-236. U-234 and U-235 in air chemical toxicity may be the kmitng ' factor, if the percent by weight-ennchment) of U-235 is less than 5. the concentration value for a 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months workweek Tab 6e 1. is 0.2 rnithgrams u anium per cubic meter of ser average. For any enrichment, the produ::t of the average concentrasson and time of exposure dunng a 44 hour5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months workweek shad not exceed 8x10-8 SA pCWir/mt, where SA is the specahe actMty of the wanum Inha6ed The conoeneration esiue ict Table 81 is 0.007 midigrams wanium per aJbic rneter of asr. The speerfe activity for natural uranium is 6.77x104 cunes per gram U. The specihc actMay for other mortures of U-238. U-235 and U-234, if not known, shall be:

CA=3.6x10"caanes/ gram U U<$epleted SA=(0.4+0.38 E+0.0034 E i 10** EE0.72 where E is the percentage by weight,of U-235, expressed as percent. NOTc in any case where there is a motture in air or water of more than one radionucEde, the kmiting values for purposes of this Appendia should be determned as follows: l

1. If me identity and concentranon of eact) raeonuchde in the anodure are known, the limitng values should be denved as !

sesows: oseemme, ser eacn redenudide m the macture, the raiso between the quantRy present in the motture and the ist I otherwee established in Appender B lor the specirc radionuc6de when riot in a mottse. The sum of such ratios for as the i radi emas m the mixture may not exceed "1" (Le " unity") l Exaaet.c: If radiom*a A, B, and C are present in concentrabons C., Ca. and Ce, and if the ar*=de MPC's, are MPC., and WCn. and MPCe respect #wely, then the concentratsons shau be hmned so that the fohowing relationship exists: (C,/MPC )+(C,/MPC.N(Ce/MPCe) 31

2. If either me adentity or the concentratson of any radic'iuclide in the mixture is not known, the Emitng values for purposes of Appendet B shan be; at For purposes of Tabte t. Col.1-4 x 10* '8

b. For purposes of Tabia t. Col. 2--4 x 10'

c. For purposes of Table II. Col.1-2 x 10* "

d For purposes of Table it. Col. 2-3 x 10"

3. If any of the corxhtsons speofeed t>elow are met, the corresponcing values specified below may be used n heu of those specec.ed n paragraon 2 atme.

a. If the identrty of each racionuchoe en the msxture is known but the concentration of one or more of the radionucteces en the mtxture is riot known the concentrabon herkt for the mrture is the limit speorfied in Appenckx ~B" for the radonuchde en the truxture having the lowest concentraton kmt. or

b. If the identity of eacn radonuches in the mxture rs not known. but it is known that certain raoonucades spec 4ed in Appendui "B" are not present n the esture, the concentrataon het for the modure es the lowest Concernration het specrfed in Appendix "B" for any radon clide u wruch rs not known to be absent frorn the enurture; or B-10 ODCM Rev. 16

l i 1 (D \v/ l \ l Nuclear Regulatory Commission Pt. 20 [@{ 20.1-20.602], App. C Table i Table il

c. Element (atomic number) and rsotope Col 1- Col. 2- Col.1- Col 2-pgf Water Ar ( C./ Water mn @'*0 *0 (MGl*0 ff 4 as known that $r 90. I 125. I 126. I 129. I 131 (I 133. Table N only). Pb 210, Po 210. At 211. Ra 223. Ra 224. Ra 226. Ac 227. R-a 228. Th 230. Pa 231. Th 232. Theat. Cm 248. Cf 254, and Fm 256 are not present. 9 x 10 * * .

3 x 10** If A is known that Sr 90, i 125. I 126. I 129 (I 131. I 133. Tatde N only) Pb 210. Po 210. Ra 223. Ra 226. Ra 228. Pa 231. Th nat. Cm 248. Cl 254 and Fm 256 are not present 6 x 10 * * . 2 x 10** ff k as known that Sr 90, i 129 (I 125. I 126. I 131. Table il ordy). Pb 210. Ra 226. Ra 228.Cm 2a8. and Cf 254 are not present 2 x 10* * , 6 x 10* ' If n is known that (1129. Tath II orWy) Ra 226. and Ra 226 are not preson' 3 x 10*

1 x 10* ' i si a is known that alpha <meners and Sr 90. I 129. PD 210. Ac 227. Ra 226.

Pa 230. Pu 241 and Bk 249 are not present 3 x 10" 1 x 10* " If R is known that alpha <rtrutters and Pb 210. Ac 227. Ra 226. and Pu 241 are not present 3 x 10 * " - 1 x 10*" If M is known that a4pna+matars and Ac 227 are not present 3 x 10* " 1 x 10"8 ff R is known that Ac 227. Th 230. Pa 231. Pu 238. Pu 239. Pu 240, Pu 242. Pu 244. Cm 248. Cf 249 and Cf 251 are not present 3 x to-'$ 1x10"8

4. If a nurture of radionuchdes consssts of uranium and its daughters in ore dust pnor to chemcal separation of the uranaam from the ore, the values spoofied below may be used for urartum and its daughters through radium-226. enstead of those from paragraphs 1,2. or 3 above.

a. For purposes of Table L Col 1-1x10"* pO/mi gross alpha activity; cr 5x10-" pCi/mi natwat urarwum or 75

/, s micrograms per cubic meter of ar natural uratuum. .k% b. For p' urposes of Tabie it, Col 1-3 x 10"8pO/mi gross alpha acavtty; 2x10"8pO/mi natural uraruum: or 3 nuey . por camic meter of aar natural uranium.

5. For purposes of this note, a radionuchde may be conessered as*not present m a anture if (a) the ratio of tie concentrabon of that radionuchde in the nature (C.) to the concentrahon limit for that radionuciede spoofeed in Table it of Appendet *'8" (A#C.) coes not exceed %e. (i.e. C./MPC.51/10) and (b) the sum of such rataos for all the radionuchdes conendered as not present in the rruxture does not exceed % Lt.

(C./Adac,,c,f4fpc;,,,,,,,+ g g). / \s 3 11 ODCM Rev. 16 APPENDIX C l EMS SOFTWARE DOCUMENTATION l C.1 ODCM Rev. 16 APPENDIX C EMS SOF1VARE DOCUMENTATION TABLE OF CONTENTS CONTENTS PAGES I l Effluent Management System Software Test Report for C-3 i Seabrook Station, May 1994 Cover ! 11 j 1-11 1 Resolutions of EMS Software Test Report Discrepancies C-4 l l-2 i l l Attachwent 3 Software Requirements Specification for North Atlantic C-5 Energy Service Corporation, Seabrook Station, 1-35 ' Effluent Management Systems, Revision 04, FP 75486 i Technical Reference Manual, Effluent Management System C-6 l Southern Nuclear Operating Company, January 1993, 36-92 l FP 75486 ) O: l 'n l l O. ! C-2 ODCM Rev. 16 l l APPENDIX C: EMS SOFTWARE DOCUMENTATION i 1 l f l l I l ATTACHMENT 1: EFFLUENT MANACEMENT SYSTEM SOTNARE TEST REPORT FOR SEABROOK STATION, MAY 1994 l i l l l l l l l C-3 ODCM Rev. 16 rQ \J EFFLUENT MANAGEMENT SYSTEM: l SOFTWARE TEST REPORT FOR SEABROOK STATION MAY 1994 , 1 O Prepared by > . s .) C J .7/,df4 / Ifate' ' <AA . b&l fA*27/99 Reviewed by - w 3/ - 7 Approved by Date Cw Yankee Atomic Electric Company Nuclear Services Division 580 Main Street Bolton, Massachusetts 01740 l I t o 1 Table of Contents

1.0 INTRODUCTION

. . . . . .. . . . . . . . .. . . . . . . . . . . . . 1 1.1 Background . . . .. . . . . . . . .. . . . . . . . . . . . . 1 1.2 Acceptance Criteria . . . . . . . . .. . . . . . . . . . . . . 1 2.0

SUMMARY

OF FINDINGS . . .. . . . . . . . .. . . . . . . . . . . . . 2 2.1 EMS Dose and Dose Rate Conversion Factors . . . . . . . . . . . 2 2.2 Liquid Release Testing . . . .. . .. . . . . . . . . . . . . 4 2.3 Gaseous Release Testing . . . .. ... . . . . . . . . . . . . 4 3.0 TEST CONCLUSIONS . . .. .. . .. .. . .. . . . . . . . . . . . . 7 4.0

SUMMARY

OF DISCREPANCIES . . . ... . ... . . . . . . . . . . . . 9

~

References . . . . . . . . . .. . ... . . . . . . . . . . . . . . . . 11 1

0 1

11 !

1.0 INTRODUCTION

\

Software testing as described in Reference [1] has been conducted for the Seabrook Station version of the Canberra Effluent Management System (EMS) . The results and conclusions are presented in this report.

1.1 Background

Canberra Industries Inc. developed the EMS software to assist nuclear power plant personnel track effluent emissions and perform associated dose

! calculations. North Atlantic Energy Service Corporation purchased a Seabrook-specific version the Canberra EMS software which must meet specific requirements l and incorporate site-specific information provided in the Offsite Dose i

Calculation Manual (ODCM) [2]. Software testing was conducted to provida assurances that the Seabrook EMS program produces results which are consistent with current ODCM assumptions and methods. All executions of the EMS program vere performed at Seabrook Station on the target software. All executions of i Oi ODCM Method II were conducted at Yankee Atomic Electric Company in Bolton, Massachusetts.

1.2 Acceptance Criteria The operability of the EMS software will be accepted if (i) information contained in the EMS data files is consistent with the ODCM, (ii) test results from the EMS program are consistent with results from ODCM methods, (iii)

Technical Specifications requirements are met by the EMS softvare, and (iv) the EMS software meets design specifications.

l Final user (Seabrook) acceptance is contingent on Seabrook approval of verification testing results and criteria established by user needs.

l 1

.' 1 2.0

SUMMARY

OF OBSERVATIONS l The EMS software tcsting included (i) identifying appropriate meteorolo5 i cal set up data. (ii) review of dose and dose rate conversion factor development, (iii) assessments for liquid releases, and (iv) assessments for i gaseous releases. ODCM Method I was used initially to confirm dose results from the EMS program. However, the simplified nature of ODCM Method I made it difficult to change the values of various parameters or obtain meaningful comparisons (other than " bottom line" comparisons). The more adaptable ODCM method, Method II, was then used to confirm EMS doses. Observations made during the software testing are sunnmarized below.

2.1 EMS Dose and Dose Rate Conversion Factors The EMS software uses precalculated conversion factors which are contained in a data file. The dose conversion factors for both liquid and gaseous effluent releases were developed for four age groups (adult, teen, child and infant), and for specific organs (bone, liver, total body, kidney, lung, GI tract and skin).

The liquid release dose conversion factors in the EMS program are the summation of the .:omponents for water recreation and ingestion of aquatic foods. The gaseous release dose conversion factors are exposure pathway-specific (e.g. ,

inhalation, ground plane, milk ingestion, etc. ) .

Dose conversion factors are provided in the EMS program for all exposure pathways addressed in the ODCM. The development of all dose conversion factors in the EMS pro 5 ram followed the pathway-specific equations in the Effluent Manarement System Technical Reference Manual [3] . The EMS conversion factors for 1 several radionuclides were examined to determined that the development process was consistent to the Technical Reference Manual and the ODCM.

2 l

p 2.1.1 Liquid Release Dose Conversion Factors

O Although the individual components for the ingestion of aquatic foods were found to be consistent with the ODCM, a discrepancy was discovered in the water recreation component. The mixing ratio for shoreline activity used in the

-development of the EMS dose factors is equal to 0.025. While this value is ,

inconsistent with ODCM Method I (which employs a mixing ratio of 0.1), it is I consistent with ODCM Method II. It is identified as a discrepancy because it is unclear which set of ODCM assumptions (those for Method I or those for Method II) the EMS program is expected to adopt.

2.1.2 Gaseous Release Dose Conversion Factors The EMS program uses dose conversion factors from Regulatory Cuide 1.109 for assessment of noble gas releases. The dose factors in the EMS program were I l

verified against and found to be consistant with Table B-1 of Regulatory Guide 1.109 (4).

The davelopment methods for the other gaseous dose factors (i.e., for inhalation, ground plane, milk ingestion, seat ingestion, and ingestion of l vegetables) were reviewed against applicable equations in the Technical Reference Manual and information in the ODCM. It is noted that the dose factors for ingestion of milk and meat are based on the fraction of year that animals are allowed to graze on pasture land (Fp) equal to 1.0. This is not consistent with the ODCM which calls for the use of an Fp value equal to 0.5.

The dose conversion factors in the EMS program for gaseous releases incorporate a shi,elding factor (SF) equal to 1.0. The EMS program is designed with a way of changing the value of SF (via use of the Options Table), but the factor is applied uniformly to both doses and dose rates. In contrast, the ODCM calls for the use of different values for SF in the calculations for doses and 3

(

I

\ . -

l dose rates.

l

, 2.2 Liquid Release Testing i

Dose estimates from the EMS program for hypothetical liquid effluent discharges (containing single nuclide and radionuclide mixtures) are nearly identical to results f' rom ODCM Method II when input data are based on the same mir.ing ratio value, indicating that the calculation method used in the EMS 1

program is consistent with the ODCM. Additionally, the EMS routine (s) responsible for liquid effluent concentrations comparisons to MPC values and monitor set point determinations was observed to be ope: ating properly.

2.3 Caseous Release Testing The agreement between estimates for total body dose rates, skin dose rates, and air (gamma and beta) doses due to emission of noble gases from the ODCM methods and the EMS program is excellent, indicating that the EMS calculation method is consistent with the ODCM.

There is also excellent agreement between inhalation doses from the EMS program and ODCM Method II indicating that, for the inhalation pathway, the calculational method and assumptions in the EMS program are consistent with those in the ODCM. The evaluation of the dose estimates via inhalation pathway i

included both long and short release durations for an elevated (mixed mode) and !

a ground level release point. The excellent agreement between the EMS and ODCM Method II also confirms that the release duration adjustment term, t-*, is applied properly in the EMS program. However, an incorrect receptor location was reported on the EMS printout in the tests (D-2c and D-2d) in which the Plant Vent was changed to be recognized as a ground level release point.

Also noted during testing was that the EMS routine (s) responsible for l calculating effluent concentration-to-MPC ratios and radionuclide release rates 1

4 t

1 l

b__________.______.__________________________._.._______._.

I

appears to be operating properly for gaseous releases.

l The EMS program incorporates the assumption that the fraction of elemental iodine is equal to 1.0 (consistent with NUREC-0133 [5)). In contrast, the 1

fractico of elemental iodine is assumed equal to 0.5 in the ODCM methods I (consistent with Regulatory Guide 1.109). Consequently, the EMS program produces dose estimates due to radiciodine that are at least a factor of two rrester than doses froia the ODCK methods. This difference increases to about a factor of 4 when the current values for Fp and SF assumed in the EMS prograa and ODCM methods are used in the dose calculations. The different assumptions for elemental iodine fractions should not present a prob'.am because each pregram is based on NRC guidance: the EMS is based on NUREr.0133, the ODCM methods are based on Regulatory Guide 1.109. The EMS program takes the more conservative approach for determining doses from radiciodine.

Making appropriate adjustments for Fp, SF, and the fraction of elemental iodine (when radioiodine input was used) and comparing results for organ doses due to I131, H3, Co60 and Cs137 revealed that the calculational methods used in the EMS program are consistant with the ODCM for all exposure pathways (i.e.,

ground plane, inhalation, milk ingestion, meat ingestion, and vegetables ingestion).

Technical Specification 3.11.2.1 and the ODCM require the calculation of

, organ dose rates due to effluent discharges of 1131, I133, H3 and particulates l

with a half-life greater than 8 days. However, in all test cases involving these l types of nuclides, organ dose rate information did not appear on Page 4 of the 1

EMS printout. Instead, the message "No calculations performed - check Ssaple &

Receptors" appeared. The EMS set up data and input were reviewed with no I

apparent error identified. Since the test cases included Cs137, Co60, I131, and S \

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H3, the missing dose rate information was urtexpected. It is noted that organ dose rate information was provided on Page 4 of the EMS printout during a demonstration of the EMS program prior to testing.

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3.0 TEST CONCLUSIONE .

Although the dose conversion factors are based on information which is not j 1

completely consistent with the assumptions in the ODCM, the calculational methods I I

used to determine doses from liquid and gaseous effluent discharges are consistent with the ODCM methods.

Other conclusions are:

1. As stated in Section 2.1.1, the development of the EMS liquid effluent dose factors is consistent with ODCM Method II, but not with Method I due to the mixing ratio value. If the EMS program is intended to be a hybrid method, the dose factors are consistent with the ODCM and are acceptable.

On the other hand, if the EMS program is intended to provide automated ODCM Method I calculations, then the dose factor should be recalculated using a mixir g ratio for shoreline activity equal to 0.1,. j

2. Since the EMS program is not designed to support the use of two O

V shielding factors * (one for dose rates and one for doses), use of a shielding factor equal to 1.0 is acceptable with the understanding that, j I

although the dose rates produced by the EMS program will be consistent with the ODCM, the 49.311 from the EMS pro 5 ram will be based on a more conservative assumption than doses from the ODCM methods.

3. Under the normal ODCM assumption for elemental iodine, the results from the EMS program will be at least a factor of two greater than results from the ODCM methods. The different assumptions regarding the elemental iodine fraction do not present a problem because each program is based on l NRC guidance: the EMS program is based on NUREC-0133, and the ODCM is based on Regulatory Cuide 1.109. Of the two methods, the EMS program takes the more conservative approach toward estimating doses from 7

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i radioiodine in gaseous effluent. -

4. The radiation monitor set point determination method for liquid releases produces a set point value that is consistent the ODCM set point method.

5. The EMS routine that is responsible for comparison of liquid effluent concentrations and MPC values is operating properly.

6. T1w release duration adjustment term, t-*, is used consistently to the ODCM.

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I 4.0 SITiefARY OF DISCREPANCIES .

l Discrepancy Area of Impact Potential Solution (s) l Mixing ratio for Doses associated with Clarify whether the EMS shoreline activity liquid effluent program is expected to used in EMS discharges, follow ODCM assumptions 1 program. for Method I or Method II. 1 If determined to follow Method I, recalculate dose i factors for liquid releases.

EMS dose factors Doses due to ingestion of Recalculate EMS dose based on Fp value milk and meat. factors for milk and meat l

vhich is not ingestion pathways to ;

consistent with incorporate Fp value ODCM. consistent with the ODCM.

Accept added conservatism in EMS in calculations of doses via milk and meat ingestion pathways.

Shielding factor Doses associated with Accept use of SF - 1.0 and (SF) applied gaseous effluent the added conservatism for uniformly to dose discharges. doses.

rates and doses in

( EMS program. Modify EMS software to accommodate use of two '

values for SF (one for ,

dose rates and one for I doses).

Incorrect receptor Potential assignment of Discuss with Canberra.

location . doses to the wrong identified on EMS receptor, printout for ground level release point.

Assumed fraction Dose estimates due to Accept added conservatism of elemental iodine in gaseous in doses due to iodine.

iodine used in EMS effluents, program differs Modify ENS software to use from ODCK methods, fraction for elemental iodine that is consistent with ODCH.

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1 Discrepancy Area of Impact Potential Solution (s)

Missing organ dose Technical Specification Discuss with Canberra, rate information required dose rate not on EMS printout calculated.

for effluent discharges containing I131, 1133 H3, and particulates.

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i, Re ferenc e s-

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1. Yankee Atomic Electric Company, Effluent Monitorine System Software Test Plan for Seabrook Station, May, 1994,

2. NAESC, Station offsite Dose Calculation Manual, Rev 13, 9/24/93.

3. Southern Nuclear Onoratine Comoany Effluent Manarement System Technical l

Reference Manual (07-0545), January 1993.

l 4 NRC Regulatory Guide 1.109, Calculation of Annumi Doses to Man from i

Routine Releases of Reactor Effluents for the Purneses of Evaluatine Como11ance with 10CFR Part 50. Annendix I, Revision I, October 1977.

5. NRC NUREG-0133 Prenaration of Radiolorical Effluent Technical ,

Snecifications for Nuclear Power Plants, October 1978.

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APPENDIX C: EMS SOFTWARE DOCUMENTATION O

ATTACHMENT 2: RESOLUTIONS OF EMS SOFTWARE TEST REPORT DISCREPANCIES O

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O C-4 ODCM Rev. 16 l

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l l Attachmint 2

/O l 2. Resolution of EMS Software Test Reoort Discrenancies l V

The following discrepancy resolutions apply to the findings contained in the {

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" Effluent Management System Test Report for Seabrook Station, May 1994" as noted on l pages 9 and 10 (see Attachment fl of Appendix C of the ODCM). With the positive i resolution of the discrepancies identified in the EMS dose code, use of EMS as a j l computerized alternative approach (designated as Method IA in the ODCM) to determine l compliance with the radioactive effluent dose and dose rate limits is acceptable since the results are comparable with the currently approved dose methods.

Discrecancy; l

Mixing ratio for shoreline activity used in EMS Program not equal to the value used

( in the ODCM Method I (Mp - 1.0) . ,

l l Resolution: l l

The mixing ratio for the shoreline activity pathway in the EMS is consistent with l the ODCM Method II approved value of 0.025, and therefore does provide for a '

j calculated dose that is within the parameters already approved in the ODCM. The use of the EMS cede (ODCM Method IA) for calculating liquid doses is acceptable for determining coy".iance with the dose limits of the Technical Specifications without the need to sc - if the assumption used for the shoreline mixing ratio.

l Discrenancy:

( EMS dose factors based on Fp (fraction of year animals are on pasture) value which is not consistent with ODCM. j l Resolution: i ODCM Method I assumes that the pasture season in the North East is 6 months long each year (Fp + 0.5). Method II allows for the pasture fraction to be set equal to 0.0 for the first and fourth quarters which equates the non-growing period of the

! year. The second and third quarters correspond to the growing season where the pasture fraction is assumed to be 1.0. The EMS software assumes an Fp value of 1.0 .

for animal grazing (meat and milk pathways) for all conditions. This is a l moderately conservative approach compared to Method I and the off grazing season conditions modeled in Method II. It is equal to the grazing season assumptions of Method II as applied in the second and third quarters. As a result, the added l

conservatism in the EMS calculations for doses via milk and meat pathways are within i

acceptable margins and guidance provided in NRC NUREG-0133 for demonstrating compliance with Technical Specification dose limits. No changes to the EMS software

are necessary.

l Discrecanev:

l l l Shielding factors (SF) applied uniformly to dose rates and doses in the EMS program.

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2. Resolution of EMS Software Test Reoort Discreoancies (Continued) l O

l Resolution:

The EMS program for gaseous releases incorporates a shielding factor (SF) equal to 1.0 for both dose rate and total dose determinations. In contrast, both Method I cnd II use a SF value of 1.0 instantaneous dose rate calculations, but a value of 0.7 for integrated doses based on assumptions in NRC Reg. Guide 1.109. The use of a SF equal to 1.0 for the external ground plane exposure pathway for both dose rate and total dose is a moderately conservative assumption that is within the bounds c1 ready assuined in the ODCM dose modeling. As a result, no modification to the EMS code as an acceptable approach (Method IA) for demonstrating compliance with Technical Specification dose / dose rate limits is required for SF.

l Discrenanev:

Incorrect receptor location identified on EMS printout for ground level release point.

lPesolution:

Incorrect name is identified on report with no impact on dose or dose rate calculations which were verified to be correct.

l Discrepanev:

Assumed fraction of elemental iodine used in EMS program differs from ODCM Methods I t_nd II.

l Resolution:

For ODCM Methods I and II, the fraction of elemental iodine assumed for gaseous releases in 0.5 based on the guidance in NRC P.eg. Guide 1.109. The EMS code assumes cn elemental iodine fraction of 1.0 based on the guidance in NUREG-0133.

Consequently, the EMS program (Method IA) will produce a moderately conservative l sstimate of dose impact (factor of 2) for iodine radionuclides if present in the l release estimations when compared to existing approved methods. As a result, no rodification to the EMS code is necessary for use in the ODCM for determining compliance with Technical Specification dose limits.

l Discrepanev:

Missing organ dose rate information on EMS printout for effluent discharges containing I-131, I-133, H-3, and particulates.

l Resolution:

This required information is easily obtainable from the permit closure process with l flashing indication if any dose or dose rate limits are exceeded.

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APPENDIX C: EMS SOF1VARE DOCUMENTATION O

ATTACHMENT 3: SOFTWARE REQUIREMENTS SPECIFICATION FOR NORTH ATIANTIC ENERGY SERVICE CORPORATION, SEABROOK STATION, EFFLUENT MANAGEMENT SYSTEMS, REVISION 04, FP 75486 l

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l O C-5 ODCM Rev. 16

O Software Requirements Specification l for l North Atlantic Energy Services Corporation Seabrook Station

. Effluent Management Systems 48-8448 Revision 04 l

Nuclear Data Systems Division Software Product O ,

Originator: y ma : //WA5 Approved: Date: /8-78 Engineering (Cl/NDS)

Approved: [ Date: 92o _y Quakty hger(CVNDS)

Approved: Date: /0 di f3 lO 7% W%

Software Requirem:nts Specificati:n RS "$ 1*-04 .

l Revision History Revision Date Description initials DJH 00 2/26/93 initialversion DJH 01 3/22/93 Updated incorrect dose

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4/30/93 Updated toinclude all dose and {

DJH 02 dose rate equabons f DJH 03 8/3/93 Updated based on modifications to software and customer's requested modification to the use of the default nuclide for gaseous Permit FM w.

DJH 04 9/14/93 Updated based on customer's request to remove moddicabon to the def ault nuclide for gaseous permit processing h

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Software R;quirements Specificati:n RS-8448-04 O 1. Scop m1

2. Applicable Documents 1

3. Interfaces 1 3.1 Hardware 1 3.2 Software 1 3.3 Human

2 3.4 Packaging 2

4. Definitions 2

5. Principal Changes from Existing Packeges 2

6. EMS Punctionality ~

4

. 6.1 Database Maintenance Transactions 4 6.2 Editing Values through INGRES QBF 7 6.3 Uquid Pre-Release Processing 8 6.3.1 UserIntertaos and Functionality 8 6.3.2 Associated Reports 9 6.3.3 Underlying Calculations 10 6.4 Uquid Post-Release Processing 11 6.4.1 Userintertaos and Funcbonality 11 6.4.2 Amandaw Reports 12 6.4.3 Underlying Cahnations 12 6.5 Uquid Permit EditirMI 13 6.5.1 User interface and Funcbonality 13 6.5.2 Associated Reports . 13 6.5.3 Undertying Calculations 13 g 6.6 Uquid Permit Deletion 13 6.7 Gaseous Pre-Release Processing 14 6.7.1 User interface and Functionality 14 6.7.2 A=amaw Reports 15 6.7.3 Underlying Calculations 15 6.8 Gaseous Post-Release Processing 21 6.8.1 User intertaos and Functionality 21 6.8.2 A===a*M Reports 21 C.8.3 Undertying Calculations '22 6.9 Gaseous Permit Editing 27 6.9.1 Userintertaos and Functionality 27 6.9.2 A==acia*M Reports 27 j i

6.9.3 Underlying Calculations 27 6.10 Gaseous Permit Deletion ' 27 6.11 Semi-Annual Reporting 28 j 6.11.1 User interface and Functionality 28 6.11.2 EMS Trend Plots 30 6.12 End-of the-Year Data Archiving 30 6.12.1 Userinteriace and Functionality 30 j O p3 1

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l Software Requiroments Specification RS-8448-04

1. Scope g W l This document estabushes the software requirements for the Effluent Management System (EMS) software to be installed at North Atlantic Energy Services Corporation's Seabrook Station.

2. Applicable Documents 2.1 The following two documents are included as part of this SRS, and this SRS refers to speerfic sections of them:

2.1.1 "Southem Nuclear Operating Company Effluent Management System Operator's Manuar (07-0544), Vers!on 1, January 1993.

2.1.2 "Southem Nuclear Operating Company Efflesnt Maneaement System Technical Reference Manuar (07 0545), Version 2, Janu r 1993.

Note: The above documents contain material (including screens and report formats) imported from final manuals for other EMS packages. Utility and plant names shown on screens and reports in these manuals are not significant, since they are determined by database data that will be customized to fit the Seabrook Station's usage.

2.2 The following document is a reference source for calculation methods of the EMS software. This SRS may referto specific sections.

2.2.1 "Seabrook Station Offsite Dose Calculation Manual," Revision 12, O

January 1993.

3. Interfaces 3.1 Hardware The EMS software shall mn on the following CPU model: DEC Microvax 3100, Model 80.

3.2 Software The software shall be written under VMS version 5.4-2 or later, using INGRES version 6.4 or later. It shall be written in VAX/ FORTRAN or VAX-DCL Utility programs provided by INGRES that are installed on the hardware configuration may be used if applicable. j I

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I Software Requirements Specification RS 8448-04 4 O 3.3 Human "

The user may be expected to have received operator training from the system mananar.

Canberra /NDS, or the plant training department prior to using any part of the '

software. Knowledge of INGRES or VMS shall not be assumed. The menus of ope; ,s are intended to be seJ!$xplanatory, but an Operator's Manual shall be developed.

The user may be expe cted to have enough knowledge of USNRC-regulated nuclear power plant affluent management to provide accurate and appropriate inputs, and to determine the va5dty of the software's results.

3.4 Packaging A distribution idt will be produced for the customer. Any removable medium supported by the operating hardware delivered to the Sne7ok Station is an acceptable distribution medium.

4. Definitions l EMS - Effluent Management System. Software for determining effluent monitor setpoints, tracking activity releases and dose impacts of individual releases, and generating semi- 1 annual release reports.

SRS - Software Requirements Specification.

SNC - Southem Nuclear Operating Company

5. Principal Changes from Existing Package The following paragraphs summarize the principal changes to the existing software that are required for the Seabrook Station system, and are intended only as introductory material.

Specifics of the required Seabrook Station EMS functionality are presented in the following sections.

5.1 The EMS software will be developed by customizing the generic EMS package, in general, the most important changes from previous versions are as follows:

5.1.1 Modification to Gaseous Permit Processing to allow scaling of auclides for Plant Vent Spike release point.

5.1.2 Modification of noble gas dose rate and dose calculation methods to use a third set of X/Q values.

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l Software Requirements Specificati n RS "fiF04 5.1.3 Modification of noble gas dose rate and dose calculation methods to multiply X/O and D/O values by a factor depending on the release durauon.

5.1.4 Modification to setpoint calculations to calculate setpoints for low gamma concentration releases.

5.1.5 Mo'dification of Permit Processing to automatically correct the expected waste flow if it is greater than the calculated maximum waste flow.

5.1.6 Modification of Liquid Permit Processing to determine dilution flow rate based on the number of pumps operating. -

5.1.7 Modification of the permit reports to include Month-to-Date Cumulative Doses and Alert Setpoints.

5.1.8 Modification of Post-Release Permit Processing to update the monitor response.

5.1.9 Addition of data to database to support and control tin above operations.

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q Software Requirements Specificatitn RS-8448-04

6. EMS Functionality 6.1 Database Maintenance Transactions The functionality of the EMS Database Maintenance transactions shall be described in section 2 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.1.1 On the Release Point Setpoint transaction [EM DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

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SCAL _NUC: For a gaseous release, a flag to denote that this release point will !

have nucBde concentrations scaled so that the total concentration matches a valL7 entered by the user.

6.1.2 On the Release Point Setpoint trrnsaction [EM-DM-RP (Form 2)] and the l Discharge Point Setpoint transaction (EM-DM-DP (Form 2)] the following '

parameter shall be added to the list of those which can be entered, stored, and which appear on the pinted report for these transactions:

DILOOKUP: For a liquid release, a flag to denote that permits for this release point wlR have a selection scroon appear for the user to select the proper dilution flow for the release based on the number of pumps operating.

6.1.3 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the i Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

DEF_NUC: For a Equid or gaseous release, this parameter will contain the default nuclide that will be used in setpoint calculations for low gamma concentration releases. This parameteris used in conjunction with the DEF CONC parameter.

6.1.4 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be antered, stored, and which appear on the printed report for these transactions:

DEF_ CONC: For a liquid or gaseous release, this parameter will contain the default concentration that will be used in setpoint calculations for low gamma concentration releases. This parameter is used in conjunction with the DEF_NUC parameter.

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Software Requirements Specificati:n RSESO4 6.1.5 dn the Release Point Setpoint transaction (EM DM-RP (Form 2)], and the j Dischargo Point Setpoint transaction [EM-DM-DP (Form 2)], the following i parameter shall be added to the list of those which can be entered, stored, and t

i which appear on the printed report for these transactions:

. DEF TYPE: For a liquid or gaseous release, this parameter will contain the default nuclide type that will be used in setpoint calculations for low gamma concentration releases. This parameter is used in conjunction with the DEF_NUC and DEF_ CONC parameters. (Note: For a gaseous release, the default nuclide type shall determine which monitor netpoint should use the default nuclide and concentration.)

, 6.1.6 On the Release Point Setpoint transaction (EM DM-RP (Form 2)), and the Discharge Point Sotpoint transaction [EM-DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:

ALRT_ SET: For a liquid or gaseous release, this parameter will contain the multiplier to be used in the calculation of Alert Alarm Setpoints for permit reports.

6.1.7 On the Release Point transaction [EM DM-RP (Form 1)], the meaning of the Response Option will change. When set to "Y", this option w'll denote the display of a Monitor Response window during the Post-Release Permit Processing, rather than during the Pre-Release Permit Processing. The Response Option parameter, itself, will remain unchanged for this transaction, but the response entered should include the monitor background values.

6.1.8 On the Dilution Streams transaction [EM-DM-DS), the following paranwters wit! be removed: the number of extra dilution flow rates and the four dilution flow rates.

These parameters will be replaced with two column fields. One column will contain the dilution flow rate, while another will contain the pump configuration description (such as " Jockey Pump

or"5"). In this transaction, the dilution flow rate for particular pump configuration can be added.

6.1.9 On the Meteorological Data transaction [EM-DM. ME (Form 1)], several menu <

options will added to the ist of MET DATA TABLES. These addtional menu items- l are as follows:

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X/O - Noble Gases (Gamma)

'a' Factor - D/O-Part/lodines l

'a' Factor- Noble Gases "a" Factor - X/Q-Part/lodines "a" Factor - Gamma Noble Gases l

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Software Requirements Specification RS-8448-04 6.1.10 On the Meteorological Data transaction [EM-DM-ME (Form 1)], the following menu items will be used to store short-term (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) D/O and X/O values.

D/O - Parbcs/Radiciodines X/O - Partics/Radioiodines X/C - Decayed Noble Gases X/Q - Noble Gases (Gamma)

Note: This specification item on!y denotes a change in the meaning for the values on this transaction and requires no further change? to the softwara.

6.1.11 On the Meteorological Data transaction [EM-DM-ME (Form 1)), the X/Q, D/0, and "a" Factor values are defined for various elevations, distances, and directions from the plant vent or stack. This combination with the

" mode of release" parameter on the Release Point transaction [EM-DM- i RP (Form 1)], and the receptor definition on the Gas Receptors j transaction [EM-DM-GR], allow the X/Q, D/Q, and "a" factors to be i different for each receptor arad/or release point.

Note: This specification item is only for clarification and no additional code changes need to be made to this transaction.

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Software Requirements Specificatlin RS*if W 6.2 Editing Values through INGRES QBF in addition to the interactive forms-based EMS Database Maintenance transcctions, certain flags and values must be edited through INGRES QBF on the database tables which contain data not accessible through the forms-based transactions.

6.2.1 Some columns of the Quarterly Dilution Volume table (ODVOL), which has no other use in the Seabrook Station version of EMS, will be used for recording monthly dilution volume for use in semi-annual reports. Once per month, an authorized user will use QBF to append a record to the ODVOL table as follows:

sampleid (sample ID) 0 (not used) dvdate (dilution volume date) The first day of the month to which the volume applies (time not requwed).

tvol Dilution volume for the month, in user (total volume) units.

aflow (average flowrate) 0 [not used]

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Software Requirements Specificati:n RS-8448 04 6.3 Liquid Pre-Release Processing 6.3.1 User interface and Functionality Uquid Pre-Release Processing functionality for the EMS software shall be as described in saction 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.3.1.1 On the Uquid Permit Deinition Screen (Screen 3.04):

i Upon entering the permit definition screen, if the DILOOKUP parameter is l set to T for the release point associated with the current permit being processed, the Dilution Flow Rate parameter will default to zero.

If a user uses the " Tab' or "Retum" key to exit the Dilution Flow Rate parameter on the Permit Definition Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of l data will appear. One column will contain the pump configuration description, while the other will contain the dilution flow rate for each associated pump configuration.

Upon selection of the Dilution Flow Rate, the selection screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter.

6.3.1.2 On the Uquid Permit DeAnttion Screen (Screen 3.04):

When a " Fill" (F14) or a "Save" (F10) without a " Fill

ls executed, if the DILOOKUP parameter is set to Y for the release point associated with the cunent permit being processed and the Dilution Flow Rate parameter is set to zero, a selection screen, as described above will appear.

Once a selection of the Dilution Flow Rate is complete, the selection screen will disappear and the " Fill" operation will continue. Upon complebon, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Pom1it Definibon Screen.

If the Dilution Flow Rate parameter on the Permit De5nition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will proceed as normal without the dilution flow rate selection screen appearing.

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Software Requirements Specificati::n RS-8448 04 6.3.1.3 Prior to entering the Uquid Permit Approval Screen (Screen 3.09):

If it is determined that the computed maximum waste flow is less than the ;

i anticipated waste flow, the anticipated waste flow will be changed to have '

the value of the computed maximum wasta flow. If the anticipated waste flow is modified, setpoint, dose, and dose rate values will be recalculated based on the new value. l 6.3.1.4 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be used for setpoint calculations. This default concentration will not be used j for updating curie, dose rates, or dose totals. ,

I The default nuclide will be attained from the DEF_NUC parameter. The j default concentration for this nuclide will be attained from the i

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DEF_ CONC parameter. The default type for this nuclide should be I

attained from the DEF_, TYPE parameter.

1 6.3.1.5 The Monitor Response Screens for Release Points and Discharge Points )

(Screen 3.08) will no longer appear while processing a Pre-Release {'

Permit when the Response Option is set to "Y" on the Release Point transaction [EM-DM-RP (Form 1)).

6.3.2 Associated Reports Liquid Pre-Release Permit Reports'shall be as described in sectio 13 (pages 3 53 through 3-58) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.3.2.1 On the Pre Release Permit Report (3.01), the Cumulative Month-to Date Doses will appear on tae page with the report category of Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all "Open" and " Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.3.2.2 On the Pre-Release Permit Report (3.01), an Alert Alarm Setpoint will appear below the Max Monitor Setpoint Value. The Alert Alarm Setpoint will be calculated by using the multiplying the release point setpoint value by a multiplier specifiod with the ALRT_ SET parameter mentioned above.

6.3.2.3 On the Liquid Special Report (3.02), an Alert Alarm Setpoint will appear below the Release Point and Discharge Point Setpoint values in the Radiation Monitor (s) portion of the report.

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i l Software Reciuirements Specificati:n RS-8448-04

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6.3.2.4 On the Pre-Release Permit Report (3.01), the calculation of setpoint data for additional dilution flow rates (under Pre-Release Calculations) will use dilution flow rate values from the Dilution Streams transaction [EM-DM-DS) for a specific dilution stream. Up to four dilution flow rates which are laroer than the diution flow rate parameter entered on the Uquid Permit Definition Screer (3.06) will be used.

6.3.3 Underlying Calculations The calculations performed by the EMS software for Liquid Pre-Release Permits shall produce the same results as those described in Chapter 2 (sections 2.1-2.6) of the EMS Technical Reference Manual (Reference 2.1.2), with no revisxxis. l l

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Software Requirements Specificatisn RS-3448-04 6.4 1.lquid Po'st-Release Processing 6.4.1 User Interface and Functionality l

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Uquid Post-Release Processing functionality for the EMS software shall be as i described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.4.1.1 On the Uquid Permit Definition Screen (Screen 3.13):

If the DILOOKUP parameter is set to "Y" for the release point and a user uses the " Tab' or "Retum" key to exit the Dilution Flow Rate parameter on the Penmit Definition Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of data will appear.

One column will contain the pump configuration description, while the other will contain the dilution flow rate for each associated pump configuration.

Upon selection of the Dilution Flow Rate, the select;on screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter.

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6.4.1.2 On the Uquid Permit Definition Screen (Screen 3.13):

When a " Fill * (F14) or a "Save" (F10) without a " Fill" is executed, if the l DILOOKUP parameter is set to "Y" for the release point associated with j the current permit being processed and the Dilution Flow Rate parameter j is set to zero, a selection screen, as described above will appear. )

Once a selection of the Dilution Flow Rate is complete, the selection screen will disappear and the " Fill

operation will continue. Upon completion, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Perrnit Definition Screen.

If the Dilution Flow Rate parameter on tne Permit Definition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will proceed as normal without the dilution flow rate selection screen appearing.

6.4.1.3 (Item removed since actual waste flow is known at time of post release processing.)

Softwort Requirements Specification RS-8448-04 O 6.4.1.4 The Monitor Response Screens for Release Points and Discharge Points (Screen 3.08) will appear wtWie processing a Post Release Permit when the Response Option is set to "Y" on the Release Point transaction [EM-DM-RP (Form 1)]. These screens will appear following the Nuclide Concentration Screen (Screen 3.15). The monitor response values entered should include the monitor background values.

6.4.2 Associated Reports Liquid Post-Release Permit Report shall be as described in section 3 (pages 3-59 through 3-62 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.4.2.1 On the Post-Release Permit Report (3.03), the Cumulative Month-to-Date Doses will appear on the page w'ith the report category of Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all "Open" and "Closod" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.4.3 Underlying Calculations O The calculations performed by the EMS software for Liquid Post-Release Permits shall produce the same results as those described in Chapter 2 (sechon 2.7) of the EMS Technical Reference Manual (Reference 2.1.2), with no revisions.

I l

i l

O W

Software Requirements Specificati:n RS-8448-04 6.5 Liquid Permit Editing g 6.5.1 User interface and Functionality Functionality for editing liquid permits through the EMS software shall be as described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

The appearance and functionality of the liquid permit definition screen and the monitor response screen shall be modified as described for the Pre-Release stage in sections 8.3.1 and 6.4.1 above.

6.5.2 Associated Reports The permit report format and contents for edited open and closed liquid permits shall be as specified above for otiginal permit reports, in sections 6.3.2 and 6.4.2.

respectively.

6.5.3 Underlying Calculations The calculation methods for editing open and closed liquid permits shall be as specified above for original calculations, in sections 6.3.3 and 6.4.3, respectively.

6.6 Liquid Permit Deletion g Functionality for deleting liquid permita through the EMS software shall be described section 3 or the EMS operator's Manual (Reference 2.1.1).

1

~

1

Software Requirsm:nts Specificatitn RS-844S 04 1

6.7 Gaseous Pre-Release Processing 6.7.1 User interface and Functionality Gaseous Pre-Release Processing functionality for the EMS software shall be as described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:

6.7.1.1 On the Gaseous Permit Definition Screen (Screen 4.05):

The Initial Pressure and Final Pmssure parameters shall be deleted. ,

6.7.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.06):

If the SCAL _NUC parameteris set to "Y", when exiting the Concentration Screen by hitting " Process" (Do), the user will be prompted for the total I nuclide concentration of permit. The concentrations are then ' scaled' !

and then stored intemally. As a result, the concentrations displayed on the screen will remain unchanged. (See the Underlying Calculations section for Pre-Release Permit Processing for an explanation of the

' scaling" of concentratons.)

NOTE:"This method requires the VAX_GSP (F12) file transfer has p occurred bdnging the representative nuclide concentration values to the Q screen prior to "Save" of data.

6.7.1.3 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be 1 used for setpoint calculations. This default concentration will not be used for updadng curie, dose rates, or dose totals.

The default nuclide will be attained from the DEF_NUC parameter. The default concentration for this nuclide will be attained from the DEF_ CONC parameter.' The default type for the default nuclide should be attained from the DEF_ TYPE parameter.

6.7.1.4 The Monitor Response Screens for Release Points and Discharge Points (Screen 4.08) will no longer appear while processing a Pre-Release Permit when the Response Option is set to "Y" on the Release Point transaction [EM-DM-RP (Form 1. 6.7.1.5 Prior to entering the Gaseous Permit Approval Screen (Screen 4.09): If it is determined that the computed maxirnum waste flow is less than the anticipated waste flow, the anticipated waste flow will be changed to have the value of the computed maximum waste flow. If the anticipated waste flow is modified. setpoint, dose, and dose rate values will be recalculated based on the new value. O *

                                                         ~W\7

Software Requirements Specificati;n RS-8448-04 6.7.2 Associated Reports Gaseous Pre-Release Permit Reports shall be as described in section 4 (pages 4- f 49 through 4-58) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: 6.7.2.1 On the Pre-Release Permit Report (4.01), the Cumulative Month-to-Date Doses will appear on the pages with the report estegory of Cumulative l Dose at Site Boundary and Cumulative Maximum Individual Dose for j Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses.for all"Open' and

                                                                               " Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" mw of doses.

6.7.2.2 On the Pre-Re' ease Permit Report (4.01), the ' scaled" noble gas concentrations shall appear on the isotopic Identification page of the report if the SCAL __NUC parameter is set to "Y" for the release point where the release is being made. l 6.7.2.3 On the Pre-Release Permit Report (4.01), the Noble Gas Alert Alarm i Setpoint will appear below the Max Monitor Setpoint values. The Alert j Alarm Setpoint will be calculated by multiplying the noble gas monitor setpoint value by a multiplier specified with the ALRT__ SET parameter mentioned above. 6.7.2.4 On the Gaseous Special Report (4.02), the Noble Gas Alert Alarm Setpoint will appear below the Release Point and Discharge Point Setpoint values in the Radiation Monitor (s) portion of the report. It will be calculated as mentioned above. 6.7.2.5 On the Pre-Release Permit Report (4.01), the initial and Final Pressure parameters will be removed from the Pre-Release Data section of page one of the report. , 6.7.3 UnderlyinD Calculations The calculations performed by the EMS software for Gaseous Pre-Release Permits shall produce the same results as those described in Chapter 3 (section i 3.1-3.6) of the EMS Technical Reference Manual (Reference 2.1.2), with the following revisions and clarifications: h

Software Requirements Speelficatlan RS-8448-04 6.7.3.1 Dose Calculations will appear in the site specific technical reference f3 V manua' a follows: , j For Noble Gas Total Body Dose Rate (for vents or stacks < 80 meters): Dt = shf + X/Qg + 8760 a , pg. I (Kg + Orgy) where Dt = the total body dose rate due to gamma emissions by noble gas releases from vent v (mrom/yr) shf = shieldng factor (dmensionless) QRiy = release rate of noble gas radionuclides,1, in gaseous effluents from vent or stack v ( pCi/sec). Fo = occupancy factor defined for the receptor at the given location (dimensionless) Kg = total body dose factor due to gamma emissions for noble ; gas radonuclide I (mretrVyr per pCl/m3 ) j X/Qg = highest value of the noble gas 1-hour X/Q for gamma radiation for vent or stack v at the site boundary, (sec/m3 ) O 8760-a = adjustment factor used to convert the 1-hour X/O value to : an average 1 year X/O value (dimensionless) where 8760 = number of hours in a year

                                   -a        =    "a" factor for gamma noble gas X/O                    ,
                                                                                                        )

For Noble Gas Total Body Dose (for vents or stacks < 80 meters):

shf . Fo . I (Kg Orgy) + X/Qg+ t a Dtb 5 (5.256 + 10 / dur) . where Dtb

                                      =    total body dose from gaseous effluents (mrom)                l 1

5.256 + 105 = number of minutes in a year dur = duration of the releate (minutes) O y \@

Software Requirements Cpecificati:n RS-8448-04 l l I t-a = adjustment factor to convert the 1-hour X/Q value to the l short term X/O value for the release (dimensionless) l where l t = duration of release (hours) a = *a* factor for gamma noble gas X/O For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters): i Ds= sht F *o I QRjy - [(L;

X/O + 8760-b) + (1.11M X/Q g 8760-a))

where Ds = skin dose rate from gaseous effluents (mrem /yr) X/O = highest value of the noble gas 1-hour X/O for vent or stack V atthe site boundary (sec/m3) Mj = air dose factor due to gamma emissions for noble gas l radionuclide I(mradlyr per pCl/m3) 1.11 = conversion factorfrom mrad to mrem , .Lj = skin dose factor due to beta emissions for noble gas radionuclide I (mrem /yr per pCi/m3) b = *a" factor for noble gas X/O

                    . For Noble Gas Skin Dose (for vents or stacks < 80 meters):

shf . Fo I QRjy . ((L; . X/Q . t-b) + (j,j j y; X/Qg* t-a)) l l Dg = 5 (5.256 10 / dur) where Dsk

                                    =    total skin dose from gaseous effluents (mrem) 9
                                                     +

D0 I

l

                                                                                                        \
   ' Software Requirements Specificati:n                                               RS4448-04

For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters):

Dy = 4 (3.17 + 10 ) . X/Q g t-a . go . g y; o,v where Dy = total gamma air dose from gaseous effluents (mrad) 3.17 + 104 = inverse of number of seconds in a year Ojy- = release of noble gas radionuclides,I,in gaseous effluents from vent or stack v (pCI) Ojy r. ORiy

dur
80 where 60 = number of seconds in a minute For Noble Gas Air Dose due to beta radiation (for vents or stacks <

80 meters): Op = (3.17

104 )
X/O a t-b . op . I N i
Ojy where Dp = total beta air dose from gaseous effluents (mrad)

Ni = air dose factor due to beta emissions for noble gas radionuclide I(mradlyr per yCl/m3)

                           -  For Critical Organ Dose Rate-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters):

DRra = X/Or 8780'C I Pipta

ORjy where DRTa = dose rate for age group a and organ i from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrerrvyr)

P ipta = dose factor for each radionuclide 1. pathway p, organ T, and age group a (mrem /yr per pCl/m ) O gM

Software Requirements Specificati:n RS-8448-04 X/O r = highest value of the radioiodine/ particulate 1 hour X/O for ! vent or stack V at the site boundary (sec/m3 ) c = "a" factor for Radiciodine/ Particulate X/O Note: It is assumed P ipra will not contain long term X/O or D/O l values.

For Critical Organ Dose Rate--Ground and Food Pathways (for vents or stacks < 80 rneters): DRra = D/O *8760d.IRip r a O R;y where D/O = highest distance ofvalue the siteof the 1-hour boundary (1/m dep)osition factor at the d = "a" factor for D/O R ipra = dose factor for each radionuclide i, pathway p, organ T, and age group a (m2. mrem /yr per pCl/sec) Note: It is assumed R ipra will not contain long term X/O or D/O values. For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters): D ra = (3.17 10-8), xfo r t* + F o I P pra *Qiy where , D ra = dose for age group a and organ i from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem) . l Note: It is assumed P ipta will not contain long term X/O or D/O values.

"h

Software Requirements Specificati:n RS-8448-04 (

 \
                       +   For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters):

D ia = (3.17 + 10-8) . D/O + td+F+IR o ipta *Oiv Note: It is assumed R ipta will not contain long term X/O or D/O values. 6.7.3.2 On the Nuclide Concentration Screen (Screen 4.06), nuclide concentrations will be " scaled" If the SCAL _NUC parameter is set property for a Release Point. This " scaling" is described as fouows: C new = (t / s)' + C; where

                          'Cinew = concentration (tJter" scaling") of nuclide; a        = sum of all nuclide concentrations on the Nuclide Concentration Screen, t        = total nuc5de concentration entered by the user C;       = concentration (before "scaEng") of nuclide;

(

 \  ..

l l l l l Software Requirements Specificati:n RS-8448-04 6.8 Gaseous Post-Release Processing 6.8.1 User interface and Functionality Gaseous Post-Release Processing functionality for the EMS software shall be as described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: 1 6.8.1.1 On the Gaseous Permit Definition Screen (Screen 4.14): t The Initial Pressure and Final Pressure parameters shall be deleted. 6.8.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.15): , if the SCAL _NUC parameter is set to "Y", when exiting the ConcentraPn Screen by hitting " Process" (Do), the user will be prompted for the total nuclide concentration of permit. The value entered for the { total nuclide concentration while opening the permit shall be displayed as { a default value which can be modified. Once the value is l enterod/ accepted the concentrations are then " scaled" and then stored { internally. As a result, the concentrations displayed on the screen will remain unchanged. (See the Underfying Calculations section for Post-Release Permit Processing for an explanation of the ' scaling" of . concentrations.) NOTE:'This method requires the VAX_GSP (F12) file transfer has occurred bringing the representative nuclide concentration values to the screen prior to "Save" of data. 6.8.1.3 The Monitor Response Screens for Release Points and Discharge Points (Screen 4.08) will appear while processing a Post Release Permit when the Response Option is set to "Y" on the Release Point transaction [EM. DM-RP (Form 1)]. These screens will appear following the Nuclide Concentration Screen (Screen 4.15). The monitor response values should include the monitor background values. . 1 6.8.1.4 (Item removed, since actual waste flow is known at time of post release ) Processing.) 6.8.2 Associated Reports Gaseous Post-Release Permit Reports shall be as described in section 4 (pages 4-58 through 4 63) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: O kh f

l l

i Software Requirements Specification RS-8448-04 1 O . 6.8.2.1 On the Post-Release Permit Report (4.03), the Cumulative Month-to-Date Doses will appear on the pages with the report category of Cumulative Dose at Site Boundary and Cumulative Maximum individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all'Open" and

                             " Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.

6.8.2.2 On the Post-Release Permit Report (4.03), the " scaled

noble gas concentrations shall appear on the isotopic Identification page of the report if the SCAL._NUC parameter is set to "Y" for the release point where the release is being made.

6.8.2.3 On the Post-Release Permit Report (4.03), the initial and Final Pressure parameters will be removed from the Pre-Release Data section of page one of the report. 6.8.3 Underlying Calculations The calculations performed by the EMS software for Gaseous Post-Release Permits shall produce the same results as those described in Chapter 3 (section 3.7) of the EMS Technical Reference Manual (Reference 2.1.2), with the following O revisions and clattfications: 6.8.3.1 Dose Calculations will appeGr in the site specific technical reference manual as follows: ! For Noble Gas Total Body Dose Rate (for vents or stacks < 80 meters): Dt = shf + X/Q g

87604
o F
I (Kg ORiv) where Dt = the total body dose rate due to gamma emissions by noble gas releases from vent v(mrem /yr) shf = shieldng factor (dimensionless)

ORjy = release rate of noble gas radionuclides,I,in gaseous effluents from vent or stack y ( pCi/sec). Fo = cccupancy factor defined for the receptor at the given location (dimensionless) Ki

                                          =   total body dose factor due to gamma emissions for noble gas radionuclide I (mrem /yr per pCi/m3)
                                                       .n.       i   u as

Software Requirements Specificati::n RS-8448-04 X/Q g = highest value of the noble gas 1-hour X/O for gamma radiation for vent or stack V at tho site boundary, (secim3) 8760-a = adjustment factor used to convert the 1-hour X/O value to an average 1 year X/O value (dimensionless) w',are 8760 = number of hoursin a year a = "a" factor for gamma noble gas X/O For Noble Gas Total Body Dose (for vents or stacks < 80 meters): shf . Fo + I (Kg QRiy) . X/Qg . t-a Dtb 5 (5.256 10 / dur) where D tb = total body dose from gr.seous effluents (mrem) 5.256 10 =5 number of minutes in a year dur = duration of the release (minutes) 14 = adjustment factor to convert the 1-hour X/O value to the short term X/O value for the release (dimensionless) where t = duration of release (hours) a = "a* factor for gamma noble gas X/O a For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters): D3= shf

F o+ I QRiy+[(Q X/O +8760 4) + (1.11Mi X/O g* 8760-a))

where Ds = skin dose rate from gaseous effluents (mrem /yr) X/O = highest value of the noble gas 1-hour X/O for vent or stack V at the site boundary (sec/m3) 23

Software Requirements Specification RS-8448-04 O

Mi = air dose factor due to gamma emissions for nobio gas radionuclide I(mrad /yr per yCi/m3) l 1.11 = conversion factor from mrad to mrom L = skin dose factor due to beta emissions for noble gas radionuclide I(mrem /yr per pC1/m3) b = "a* factor for noble gas X/O a For Noble Gas Skin Dose (for vents or stacks < 80 meters): shf + Fo I QR y * [(L;

X/O +41 ) + (1.11M; XO g t-a))

Og = 5 (5.256 10 / dur) I where Dsk = total sidn dose from gaseous effluents (mrom) O

For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters): Dy = (3.17 + 10-8) . X/Q g a t-a , op . g y, , o;y where Dy = total gamma air dose from gaseous effluents (mrad) 3.17*104 = inverse of number of seconds in a year Qy = release of noble gas radionuclides, I, in gaseous effluents from vent or stack v (pCl) Oy = QR y* dur

60 where 60 = number of seconds in a minute O

24-

Software Requirements Specificati:n RS-8448-04 For Noble Gas Air Dose due to beta radiation (for vents or stacks < 80 meters): Dp = (3.17 10-8). yjg . t-b . p0 . I Nj Ojy where Dp = total beta air dose from gaseous effluents (mrad) Nj = air dose factor due to beta emissions for noble gas radionuclide I(mradlyr per pCl/m3)

                    -   For Critical Organ Dose Rate--Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 rneters):

DRra = X/Or

8760-c . g pi Ta
OR y where DRra = dose rate for age group a and organ r from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrem /yr)

Pipra = dose factor for each radionuclide I,3 pathway p, organ T, and age group a (mrem /yr per pCl/m ) X/O r = highest value of the radiolodine/ particulate 1-hour X/O for vent or stack V at the site bourktary (sec/m3 ) c = *a* factor for Radiolodine/ Particulate X/O Note: Itis assumed P ipta will not contain long term X/O or D/O values.

                      -  For Critical Organ Dose Rate--Ground and Food Pathways (for vents or stacks < 80 meters):

DRia = D/O 8760d IR ipta

O Rjy where D/O = highest value of the 1-hour deposition factor at the distance of the site boundary (1/m')

d = *a" factor for D/O 25- i

Software Requirements Cpecificatinn RS4448-04 Rjp7 a = dose factor for each2 radionuclide I, pathway p, organ r, and age group a (m , mrom/yr per yCL/sec) Note: it is assumed R ipta will not contain long terrn X/O or D/O values. For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3. C-14 (for vents or stacks < 80 meters): D ra - 4 (3.17 10 )

X/O r* t< + F o I Pipta *Oiv where D ra = dose for age group a and organ i from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrom)

Note: It is assumed Pipta will not contain long term X/O or D/O values.

For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters):

4 D ra = (3.17 = 10 )

D/O + td*F*IRo pra
Oiv Note: It is assumed Ripta will not contain long term X/O or D/O values.

6.8.3.2 On the Nuclide Concentration Screen (Screen 4.15), nuclide concentrations will be " scaled" if the SCAL _NUC parameter is set property for a Release Point. This " scaling" is described as follows: Cinew = (t / s) + C; where Cinew = concentration (after" scaling") of nuclidei s = sum of all nuclide concentrations on the Nuclide Concentration Screen, t = total nuclide concentration entered by the user C; = concentration (before ' scaling") of nuclide; y 1 Software Requirements Specificati::n RS-8448-04 6.9 Gaseous Permit Editing l 6.9.1 User Interface and Functionality . I Functionality for editing gaseous permits through the EMS software shall be ! described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: The appearance and functionality of the gaseous permit definition screen, the monitor response screen, and nuclide concentration shall be modified as described for the Pre- and Post-Release stages in sections 6.7.1 and 6.8.1 above. 6.9.2 Associated Reports The permit report format and contents for edited open and closed gaseous ' permits shall be as specified above for original permit reports, in sections 6.7.2 and 6.8.2, respectivety. 6.9.3 Underlying Calculations i The calculation methods for editing open and closed gaseous permits shall be specified for original calculations, in sections 6.7.3 and 6.8.3, respectively. l 6.10 Gaseous Permit Deletion Functionality for deleting gaseous permits through the EMS software shall be described , section 4 or the EMS operator's Manual (Reference 2.1.1). I I l 27-5 30 0 lt 1 1 I

Software Requirements Specification RS-8448 04 O 6.11 Semi-Annual Reporting l l 6.11.1 User Interface and Functionality Semi-Annual Reporting functionality for the EMS software shall be as described in ! section 5 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: 6.11.1.1 On Report 5.01 (Gaseous Summation of All Releases): l

                     +   Compute each value on line A.3 of the report by taking
                                                         .Da  ,O the greater of 3           O where D ag = the gamma air dose in the applicable quarter at the site boundary receptor due to noble gas emissions (mrem)

Dab = the beta air dose in the applicable quarter at the site boundary due to noble gas emissions (mrom) j QLag = the quarterly limit on Dag (mrem)[usually 5) QLab = the quarterly limit on Dab (mrem)[usually 10] A note will be made at the bottom of the report stating whether the beta air dose and its associated limit or gamma air dose and its associated limit were used for the Percent of Applicable Limit of Fission and Activation Products..

                      . The values on lines B.3, C.3, and D.3 will be the equivalent. They will be calculated as follows:

the greatest (overt) of 100 * (I D i ,T) / Oltp O 28-

Software Requirements Specificati:n RS 8448-04 where l Di ,T = the dose to organ T of the controlling receptor,in the l applicable quarter, due to gaseous emissions of l radionuclide1 (mrem) l The summation is over all non-noble gas radionuclides with half lives greater than 8 days, including radioiodines, l particulates, and tritium. OLrp = the quarterly limit on the controlling receptor organ dose due to gaseous effluents (mrem) [usually 7.5) 6.11.1.2 On Report 5.02 (Liquid Summation of All Releases):

For each quarter q in the report, calculate the reportable dilution volume (DVrq, in liters) for the portion of the quarter that is within the report dates. It is the sum of the reportable monthly dilution volumes (DVrm)in user units for all the months in the quarter that are within the report dates: DVrq = 28.31685

sd_tvolf . I DV rm

                       'The values DV rm are from the column tvol of the ODVOL table. The value DV rq is included in the report on line F, and is used in the calculations below.' "sd__tvolf" should be the user unit conversion factor to convert from user units to~ft3 . 28.31685 is a unit conversiore factor from it 3to Eters.

a For each space on e Lne titled " AVERAGE DILUTED CONCENTRATION DURING PERIOb", the average concentration (Cq, in pCl/mi) for the respective quarter is computed as follows (where i ranges over only the nuclidesin the category): Cq= I Cgq = I [ Actiq / (1000

DV rq )l where Actiq = total activity of nuclide i released during the portion of the quarter q that is within the period (yCl)

DVrq = reportable dilution flow for the portion of quarter q that is , within the report period (liters), as calculated above. 1 Compute each value on line A.3 and B.3 of the report by taking ; the greater of 100 / 300 - t ,0 [

                                                      '1        h l

Software Requir:m:nts Specificati:n RS-8448-04 , i O

                 ^
                          ~-

Dg = the liquid total body dose in the applicable quarter at the site boundary receptor (mrem) Djo = the liquid maximum organ dose in the applicable quarter at the site boundary (mrom) QLg- the quarterly limit on D (mrem) g [usually 1.5] Olio = the quarterly limit on Dio (mrem)(usually 5) A note will be made at the bottom of the report stating whether the liquid total body dose and its associated limit or maximum organ dose and its associated Emit were used for the Percent of Applicable Limit.

Compute each value on Ene C.3 of the report as follows: Pq= 100

Cq / Ldg where Cq = sum of noble gas concentrations Pq = Percentage applicable to a given quarter for dissolved and entrained gases Ldg = Liquid dissolved gas limit (gCl/mi) [usually 2.0E-04]

1 6.11.2 EMS Trend Plots Trend Plotting functionality for the EMS software shall be described in section 5 of the EMS Operators Manual (Reference 2.1.1) with no revisions. 6.12 End-of-the-Year Data Archiving 6.12.1 User Interface and Functionality End-of-the-Year Data Archiving functionality for the EMS software shall b described in section 6 of the EMS Operators Manual (Reference 2.1.1) with no revisions. J l Documentation Review Report Docurr. tnt Reviewed h$$ $fA3/?beK YAT)oA) $N$ k$~$ $'0h . Does the document meet the requirements or No is the document approved? or No if not please state the exceptions: I l I

O l i 1 l

l _ _ ~ . Signature: ,,

                                     ; 6fM                             Date:    "N pc34                          m,= 0 L                                                                  -

Documentation Review Report Sg4grec3z tys "TR5 [(5 - N @ - C' Document Rewowed Does the document meet the requirementsMor No

   !s the document approved? hor No u not please state the excepsons:

O ge ne O em i 0 t ,y e g signature: m> /Id/Jtt oew: 4/44:

V pamo b es2

1 APPENDIX C: EMS SOFTWARE DOCUMENTATION O l i I l ATTACHMENT 4: TECHNICAL REFERENCE MANUAL, EFFLUENT MANAGEMENT SYSTEM SOUTHERN NUCLEAR OPERATING COMPANY, JANUARY 1993, FP 75486 l O l l l i l i O C-6 ODCM Rev. 16

i

   \                                                     .

Canberra Nuclear Nuclear Data Systems Division 150 Spring Lake Drive Itasca, Illinois 60143-2096. 2 January 1993

Southern Nuclear Operating Company k Nfluent Management System Technical Reference Manual 07-0545-02 ,,

              .Yy t

( 1 0 TABLE OF CONTENTS 1 1 Pap . I

                                                      ~                                                                    l CHAPTER 1 INTRODUCTION ........................................                                       1-1           l i         1.1      SETPOINT CALCULATIONS ..................................                                    1-2 9         1.2      REL'sASE PROCESSING    .....................................                                1-3 1.3      COMPOSITE NUCLIDES     .....................................                                1-3 CHAPTER '2 LIQUID RELEASE CALCULATIONS             ..........................                        2-1 2.1      LIQUID PRE-RELEASE PERMIT .............................. 2-1 2.2      10CFR20 COMPLIANCE .....................................                                    2-1 Dissolved and Entrained Gases ......................                                   2-4 2.3      MAEIMUM WASTE FLOW .....................................                                    2-4 2.4      MINIMUM DILUTION FLOW RATE ............................. 2-5 l         2.5      SETPOINT CALCULATIONS .................................. 2-5 Reconunended Setpoint      ...............................

2-8 Setpoint in pCi/ml ................................. 2-8 l Reconunended Setpoint in User Units (e.g. cpm) ..... 2-10 Setpoint for Discharge Point ...................... 2-11 2.6 DOSE CALCULATIONS FOR LIQUID RELEASES ................. 2-12 2.7 31 DAY PROJECTED DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . . 2-14 2.8 POST -RELEASE PROCES SING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -14 .

        ' CHAPTER 3 GASEOUS RELEASE CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.1    GAS PRE-RELEASE PERMIT ................................. 3-1                                           .

l l3.2 RADIONUCLIDE ACTIVITIES AND COMPOSITE VALUES ........... 3-1 l Activity Rele'ased .................................. 3-2 3.3 10CFR20 COMPLIANCE ..................................... 3-2 l

        ,3.3a      COMPLIANCE WITH OLD 10CFR20 ............................                                   3-3 a

3.3b COMPLIANCE WITH NEW 10CER20 ............................ 3-5 p'.3.4

         .         SETPOINT DETERMINATION FROM NEW/OLD 10CFR20 ............ 3-6 l         J3.4a     NEW 10CFR20 NRATIO ..................................... 3-6 3.4b    OLD 10CFR20 NRATIO .................................... 3-11 Noble Gases ....................................... 3-11 Radiciodines and Particulates ..................... 3-11                                            )

l 3.4c SETPOINTS ............................................. 3-12 ] 3.4d REPORTED SETPOINTS ..................... .............. 3-15 j 3.5 MAXIMUM WASTE FLOW .................................... 3-16 3.6 DOSE RATE AND CUMULATIVE DOSE CALCULATIONS ............ 3-17 Noble Gas Total Body Dose Rate Calculations ....... 3-17 Noble Gas Dose Calculations .. .................... 3-18 Organ Do s e Calculation s . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -2 0 3.7 RESOLVING DOUBLE-COUNTING OF DOSE AND ACTIVITY......... 2-21 / 3.8 31 DAY PROJECTED DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . . . 3-22 GAS POST-RELEASE P ROCESSING . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -22 3 .,9 l

        .....--                                                                                                            q 1

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F i 1 l 1 CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS ......................... 4-1 4.1 POTABLE WATER .......................................... 4-2 4.2 AQUATIC FOODS PATHWAYS ................................. 4-2 4.3 SHORELINE RECREATION PATHWAY ........................... 4-3 4.4 IRRIGATED VEGETABLE PATHWAY ............................ 4-4 4.5 REDUCTION TO NUREG-0133 EQUATIONS ........... .......... 4-5 . CHAPTER 5 GAS DOSE FACTOR CALCULATIONS ...................."..... 5-1 5.1 INEAtATION PATHWAY ..................................... 5-1 J 5.2 GROUND P LANE P ATHWAY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 5.3 MILK PATHWAY ........................................... 5-2 Carbon-14 in Milk .................................. 5-4 Tritium in Milk .................................... 5-4 5.4- MEAT PATHWAY ........................................... 5-5 Carbon-14 in Heat ......................~............ 5-5 Tritium in Heat .................................... 5-6 5.5 VEGETABLE PATHWAY'...................................... 5-6 Carbon-14 i n Vegetables . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7 Tritium in Vegetables .............................. 5-7 5.6 RELUCTION TO NUREG-0133 EQUATIONS ...................... 5-7 APPENDIX A REFERENCES .......................................... A-1 r - L 4 P i .

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CHAPTER 1 INTRODUCTION The Effluent Management System (EMS) Software implements the . requirements for determining limits ,and doses for the routine liquid and gaseous releases from nuclear power plants. The calculations and methodology are based on those described in U. S. Nuclear Regulatory Commission Regulatory Guide 1.109 and references described therein. These equations reduce to those described in NUREG-0133 by proper selection of parameters. This manual describes the calculations used in the LRW/GRW program for handling liquid and gaseous releases and preparing the semi-annual report, and the equations used in the DFP option for calculating- the relevant dose factors. ) l This manual describes the new 10CFR20 (1992) as well as old 10CFR20 requirements. j For a nuclear power plant, the Off-Site Dose Calculation Manual

O (ODCM) describes the methods used at that plant for complying with the effluent release portions of the technical specifications and the requirements of 10CFR20 and Appendix I of 10CFR50.

         .       The concentration and dose limits that are required to be met are:       -

o For radioactive liquid effluents, the concentrations

             .             released to areas beyond the site boundary are limited to:
        .,q                                 ...

MFC values given in old 10CFR20, Appendix B, Table II. OR

           .                     ECL values given in new 10CFR20, Appendix B, Table 2.
        'h['.  /           where ECL valu s are effluent concentration limit values.

o, For radioactive liquid effluents, the -N= dose to any member of the public will be less than the limits given in 10CFR50, Appendix I. o For gaseous effluents, the old 10CFR20 requires that the dose rate at any location beyond the site boundary will be limited to the annual dose limits given in the Technical Specifications and corresponding to the concentrations in Appendix B of the old 10CFR20, while the new 10CFR20 requirement is that thrs diluted concentration at the site y bounchtry be less than the ECL values given in the new 10CFR20, Appendix B, Table 2.

o For gaseous effluents, the maximum dose to any member of O the public will be less than the limits given in 10CFR50, Appendix I. o The maximum dose to any member of the public will not . exceed the limits given in 40CFR190. The equations emr>1oyed for calculating the dose and dose factors are (' taken from NUREG-0133 1 and Regulatory Guide 1.109.2 For a particular nuclear plant, the ODCM describes the physical confi'uration g of release sources and release points-for routine and non-routine liquid and gaseous effluents, the monitor setpoint calculations, dose, and dose rate calculations. 1.1 SETPOINT CALCULATIONS Calculations are made for the radiation monitors to determine the alarm / trip setpoint so tha+.10CFR20 compliance is met. For the old 10CFR20 compliance, liquid calculations use the maximum permissible concentrations from 10CFR20 App. B, Table 2, column 2, and the more conservative value (smaller) of the soluble and insoluble values while gas calculations use dose rate equations and limits from NUREG-0133. To comply with the new 10CFR20 requirements, the

                                                  ' effluent concentration limits are used for both liquid and gaseous calculations.

3. In the terminology of EMS,' individual sources of radiation, such as

                                               - storage tanke, the containment building, etc., are defined as                          t
                                                    " release points." Several release points may lead to the same
                                               .' " discharge point. "

j t

                                              ' 'Setpoint calculations produce monitor limiting values in activity units (pCi/ml or pCi/cc). These are then converted to user units, e.g. counts per minute (epm).

EMS allows setpoints to be set f or both the release points and the discharge points. In the c:ase that the release point and the discharge point are the same, or use the same physical monitor, the , same discharge setpoint value is reported for both. This use of the l same. discharge setpoint value can be. disabled. EMS has a "nuclide specific" option. In this option only the nuclides listed in the monitor sicpe table are used in the setpoint j

                             .                       calculations .                                                                     l
                                                 . wp-l-2 grup yo

1.2 RELEASE PROCESSING For batch releases, the procescing of releases consists of sampling f l the tank or volume of air, analyzing the radionuclide content, then . using the radionuclide concentrations and estimated release flows, volumes, etc. and calculating the doses and setpoints, comparing to

     ,.        the 10CFR20 limits, and ebmparing to the 10CTR50 limits. If the
  ~

limits are not exceeded, the pre-release ps.cait is signed off and the release can occur. After the release, post-release processing performs the same calculations (except the setpoints are not needed) and the database is updated with the actual values for the release. For continuous releases, many installations prefer not to generate an actual pre-release permit, but for the sake of analogous j operation', ~ pre-release calculations must still be made in EMS. After review, the post-release calculations are made to update the . databe.se. l EMS does not allow more that one cpen release at a time for a single release point. However, multiple releases may be open for one discharge point. Also, for discharge points, the setpoint is calculated by summing over all open releases for the time period l' involved. -

        ,       1.3    COMPOSITE NUCLIDES                            -

i l .NThe standard radionuclide* analysis, with high-resolution germanium l l detectors, quantifies the gasuna-emitting radionuclides. Pure beta l

              , emitters, nuclides that decay by K-capture, and alpha emitters are
          .    ' handled with other detection mechanisms.          These are usually not
          ,.Y tracked individually by sample, but as a composite of many samples
             ',.'over a month or quarter period. The concentrations of the composite nuclides are combined with the concentrations of the individual nuclides determined from gansna analysis for each sample.

For liquid releases, the composite nuclides are generally H-3, Fe-55, Sr-8 9, Sr -90, sad gross alpha. For gaseous releases, Fe-55 is generally not included. In EMS, these are contained in an editable file designated by the composite ID number. Each release point definition specifies which composite ID is used with the release point. These can be the composite nuclides, or any other nuclides desired.

              ..s.'"-                                       g 1-3'      \O

} Composite samples produced by taking portions of the samples from individual releases are analyzed after the releases are over. Since these generally do not vary much from one period to the next, it is common to use the most recent values. However, EMS provides the option of updating the composite values for the proper time period and recalculating the activity and dose values in the database. -

For the setting of flags to control options in the EMS code, see the EMS Operator's Manual. e e O

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1 5- CHAPTER 2 LIQUID RELEASE CALCULATIONS 2.1 ' LIQUID PRE-RELEASE PERMIT l A liquid pre-release permit is generated with a program that uses the nuclide activities to determine the radiation monitor setpoint (for 10CFR20 compliance) and the potential doses for 10CFR50 compliance. l Continuous releases.are treated similarly. 2.2 10CFR20 COMPLIANCE I 10CFR20 compliance calculations are broken down into two paths. The

           ..first path calculates compliance with the old 10CFR20 i'n'which the
         ,i, calculations are, based on Maximum Permissible Concentrations. The second path complies with the new 10~:FR20 and is Effluent Concentration Limits based.
        ' ,10CFR20 requires that the' sum of concentrations divided by MPC (old
       '*i10CFR20) or ECL (new 10CTR20) values must not exceed unity:

OLD 10CFR20 NEW 10CFR20 S=I g Cg /MPC g s1 S=I g Cg /ECL g s1 OP.

              'f or concentrations Ci released from the site. MPC g is the maximum permissib'.e concentration from the old 10CFR20, Appendix B, Table II, Column 2, for nuclide i and ECL i is the effluent concentration limit from the new 10CFR20, Appendix B,             Table 2, Column 2, for nuclide 1.

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If the summation is greater than unity, dilution is required. The required dilution factor is:

If the 10CFR20 option is OLD: C . i Z. - urC 1 1 i D = req f*R

,. max where D req = Total required dilution factor C1 = Concentration of nuclide i in pCi/mL MPCg = Maximum permissible concentration of nuclide i in FCi/mL f = Release point setpoint safety factor (usually equal to 0.5) from the release po :. definition.

Rmax = The marimum MPC ratio from the release point setpoint definition. If the 10CFR20 option is NEW: C - 1 -

     -                                 I    ECL i=g         i D        =

3 reg,g f*R C

           .                                  i 3    EC's i                                                j p         ,i=ng req,ng       i*R D        = D                                                             j req         req,9 + Dreq,ng where Dg,3q,9    =       Required dilution f actor for ganna-emitters D reg,ng   =       Required dilution f actor for non-gamma-emitters ECL1
                                    =       Effluent concentration limit of nuclide i in           l FCL/mL                                                 l
                . .:-                                                     L 2-2                 l I

and the sums extend over gamma-emitters (g) and non-gamma-emitters (ng), respectively . Any nuclidos with MPCis 0 are excluded from the sum. ! Any nuclides with ECLi s 0 are excluded from the sum. The available dilution flow is the ndnimum dilution stream, flow that can be ensured for the period of t'he release, corrected for other releases.in process and any activity in the dilution stream, and

    't           reduced by a safety factor.                                                        !

F, = F, (f /100) (1 - I C /XXX g) f where C1-= Concentration (pCi/ml) for nuclide i for the dilution stream sample l XXXi= MPCi or ECLi fg = Flow safety factor, in percent l i F ant = Anticipated dilution f2 ow rate for the release

.)

The anticipated dilution factor is then - D ant

                                     =   (F waste +f alloc Favail J/Fwaste                           ,
           .,                                        ...                                              j
            where F ,, ,= waste, flow anticipated for this release F         = available dilution flow                                      ,

avail l 1

                       . f         a  fraction of available dilution stream flow allocated to    l alloc this release A

f )

 \_ /               .    .

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Dissolved and Entrained Gases To implement 10CFR20, it is also required that the total concentration of dissolved and entrained gases in liquid effluents be less than a specified value (normally, 2 E-04 uC1/mL under OLD 10CFR20, or 1 E-04 pCi/mL under NEW 10CFR20). EMS stores this limit , in the Activity Limits transaction, checks this limit for each liquid permit, and indicates on the permit approval screen whether or not it is exceeded. To include dissolved noble gases in the Dreg calculation, the database must also contain the same limiting value,

*~

as the liquid MPC or ECL for each gas. 2.3 MAXIMUM WASTE FLOW

     -        The maximum waste flow calculation is based on the setting of the SET _ OPT option in the WFLON_M class of options in the Release Point NONE, Setpoint definition. This option can take on four values:

NO_ WASTE, CALC or DOSE. For liquid releases, NONE, NO,_ WASTE, and CALC ara allowed. For liquid releases, Wmax = the min 4 - = of Rwmax and R ewg.ig where . Wmax = Maximum permissible waste flow rate for this release

         ?             Rwmax    = Release point maximum waste flow rate, as set in the release point definition If the SET _ OPT option = NONE:                                      ,

R cwmax = waste flow rate for the sample, Fwaste If the required dilution factor, D req . (section 2.2) for the sample is greater than 1, Rewmax becomes-Favail

falloc R-l D req - 1.0 If the SET _ OPT option = CALC

Favail

falloc + Fwaste ~

R mx

            ,.~;-
                                                          *9                                       1 2-4           %

J l i i o 1

 .\.                                                                                            i If the SET _ OPT option = NO_ WASTE                                  I Favail

falloc Rcwmar. "

D req - l 2.4 MINIMUM DILUTION FLOW RATE If Dreq > 1,.the minimum dilution flow rate is determined as l follows: l If the SET _ OPT option is NO_ WASTE: Fwaste

D reg C' '

falloc * (ff / 100) * [l-T* g ] ; XXX g j where XXXg is HPCi under OLD 10CFR20, and is ECLg under NEW 10CFR20. i\g . j If the SET _ OPT option is other than NO_ WASTE: ! Fwaste * (D req - 1.0) min dflow = i, C i [, falloc *-(ff / 100) * [l-If ] i j

             .Otherwise:
              .                                                                                 l
         <,                                                                                    1 J:                       , min _dflow = 0.0                                          )

i 2.5 SETPOINT CALCULATIONS ! i Setpoints are calculated for individual release points, and for the discharge point that may combine several release points. A setpoint adjustment factor, S adj is determined from the value of D req

l 1

             -+                      -

2., p47 ,

1 l 1 If Dreg > 1 or the dilution f actor option is N, and the sefmoint equation is set to STD: Sadj = Dant /D req If the dilution f actor option is Y, no credit is taken for dilution . (setpoint equation.39 set. to NO_DILUT) , and the setpoint adjustment factor is: E- Sadj = 1/Dreq . If neither of these conditions is true, Sadj = 0. After the e.bove tests, further tests are made based on the setting of the setpoint equation option, SETP_EQN. These may change Sadj as follows: If ~ the SETP_EQN is set to STD, and the SET _ OPT option is set to NO_ WASTE, and Fwaste > 0, then: falloc

Favail S adj "

Fwaste

D req Otherwise, if the SETP_ EON option is set to STD, and the SET _ OPT option is set to other than NO_ WASTE, and Fwaste > 0, then (falloc
Favail) +F waste S

adj " Fwaste

Dreq Otherwise, if the SETP_ EON option is set to LOW ACT, and the SET _ OPT option is set to NO_ WASTE, and Fwaste > 0, then:

(falloc

Favail)

                                       -D req,ng S

adj " D req,g f b6

a Otherwise, if the SETP_EQN option is set to LOW ACT, and the SET _ OPT option is set to other than NO_ WASTE, and Fwaste > 0, then: (falloc

Favail) +F waste

                                                        -D req,ng                  -

D req,g Otherwise, Sadj is unchanged. - The setpoint adjustment factor is further tested against a limiting value (S adj lim which is set using the Release Point transaction in Database Maintenance) . If Sadj > Sidj, h then S y$ = Sadj, lim . . All of this leads to the == setpoint value, S ,x, based $n the gamma-emitting radionuclide mix: S (pci/ml) =S max ad)..I Ci

 )       where the sum extends over all gamma-emitting nuclides (nuclides of type other than O) in which thei2; concentrations are greater than 0.
    ' In user units (cpm or other as set in the F ow Monitor Parameters transaction in Database Maintenance), the maximum setpoint is
   ,.,             S      (cpm) =  S           ~
                                                   '+

adj mon where I B = moniter background (cpm) Rmon = monitor response (epm)

                           = offset + slope a ICi + quad * (I Cs) 2 + B where offset, slope, and quad are the coefficients in a quadratic fit to the monitor response to nuclide activity.

I 2-7 b%

\ 4

EMS provides an option to calculato nuclide specific responses so that Rmon is the sum of responses for r2ch nuclide, rather than the sum of the nuclide concentrations, as shown above. In the nuclide-specific case, l I R = I (offset +g slope

Cg ,+ quadg *

(Cg )2) + B l where the sum ertends over all nuclides which have response factors l {. stored in the database for the monitor of interest. Recommended Setpoint 1 The setpoint rn?.ommended for actual use is based on a comparison of the setpoin.t calculated as above and def ault values determined by the user. The default setpoint in user units (e.g. cpm) can be defined with or without background included. If the cunitnopt parameter (defined in the release point and discharge point tables) equals 0, the def ault value does not include background; and the current background is added to the def ault value. Otherwise, the current background is not added to the default value. Setroint in DC1/ml

        .A candidate setpoint is calculated based on the erpected response:

S =f IC erp tol i . . where

     ',            f     = setpoint tolerance factor (can be set for the                                                     t release point using QBF)
                         = 2 if not specified by the user I

Now compare the S,gp value to the default table value Sdef 1 i e .-5 2-8 l

i i n v If S,xp < S max and if S <S and S sS exp def def max , then use Sdef Case 1 . i

   "..                     Otherwise use S,xp.                        Case 2,5 If S,xp 2 S max            use S m.                    Case 3 If S max      = 0, use Sdef                            Case 4                   .

Case 4 occurs if no activity is detectable in the sample (Sadj = 0) . l Case 1 case 2 Case 3 Case 4 Case 5 , S,xp - - Sdef~ ~ l I s --- s ---- sm ._. 5 ,,,,---- , S,xp S ,xp--- a . . 3def~ ~ 3def Sde f -~~ 3def - ~ S -- ly'. m

          .          0 --                  0               0--             0 --      0 Use Sdef                Use S,xp       Use S,,,        Use Sdef   Use S,xp Schematic of Liquid Setpoints (gCi/ml) v
              . wld-          .

                                                              ,                                l e1 l l

Recommanded Setpoint in User Units (e.a. com.) _ is The candidate setpoint based on expected monitor response , calculated as follows: E S exp (cpm) =f tol

                                           *  (R mon
                                                     - B) +f Btol *B where fBtol = background tolerance factor (set using QBF on the releasept table)

If the def ault setpoint value includes background: B rp =0 If the default setpoint value does not include background: Bg.p = B where B is the monitor background count rate and Brp is used below.

                               <S max   (cpm)

If S,xp (epm) 2, and if . S,xp (cpm) <Sdef (cpm) + B ,,.p and Sdef (cpm) +B rp sS max (Cpm) then use Sdef (cpm) +B rp Case 1 Case 2, 5 Otherwise, use S,xp (epm) If S exp (cpm) >S max (cpm) use S max (cpm) Case 3 l I 2-10

                                                                          '   ----_w

I l l

                                                                                    .                   l l

l l D '

l If S ,,x (cpm) = 0, use Sdet +B rp Case 4 NOTE: S max is due to concentration only (i.e., excludes background) for Case 4 ,

 'b            Setpoint for Discharoe Point For the discharge point, the total MPC/ECL fraction ist

( I C /MPC g ) *F + ( I C /MPC g ) *F F +F o OR ( I C g/ECLg) *F + ( I C /ECL g g) *F F +F o where (I Ci /MPCi )o= total MPC fraction f or existing concurrent ,

            ,                           releases for this discharge point excluding this additional release.
          ,'            IC/Wi=

i total.HPC' fraction for the new release (Z Ci /ECLi )o= total ECL fraction f or existing concurrent

            .,                          releas.es for this discharge point excluding 2
       ,                                this additional releqise.

j. -

Z Cg/ECLi= total ECL fraction for the new release ] i Fo = discharge point waste flow excluding new the j release point waste flow to be added. 1 I F= projected waste flow for the new release point I to be added O 2-11 1

The radiation monitor for the discharge point has setpoint equations identical to those presented above, except for the nuclide-specific response. For the nuclide-specific response, the concentrations are modified as in:

C =C g [F /, (F + F ) ] R + dpmon ** i+

P*i "i dpmen where CfP

                       =   the discharge point isotope concentration from this release point Rdpmon = the discharge monitor response in user units E

dpmeno= the discharge monitor response before the current release is added including the background For non-isotope specific response: R dpmon = [ offset + slope

C dP + quad * (CdP)2 ) +Rdpmen o where Cd p = ( I C ] [F/ (F+F ) )

i o

    ,26 DOSE CALCULATIONS FOR LIQUID RELEASES a
  The EMS sof tware calculates and stores the dose for each receptor, for each nuclide, and for each organ. The dose is the total over
       .all pathways which apply to that receptor. A receptor is defined by                                           ,
 ,: receptor ID, age group (infant, child, teen, or adult), sector, and Al distance from the plant.

The equation used in the liquid permit processing to calcuiate the dose received by receptor r from a released nuclide i is: D =A I at C F iTr iTr s is sr where: DiTr = the cumulative dose or dose commitment to the total body or an organ T by nuclide i for receptor r from the liquid effluents for the total time period of the release, in mrem. 2-12 i l

I ! (^ I . AiTr = site-related ingestion dose or dose conunitment factor for receptor r to the total body or organ T for radionuclide i, in mrem /hr per pCi/ml. At s = length of time period s, over which the concentration and F value are averaged, for all liquid releases, in . hours. .

      ,,                    C,=1        the average concentration of radionuclide i in undiluted liquid effluent during time period At s f*0" any liquid release, in pCi/ml.

F sr = the near field average dilution factor for receptor r

       ,                                during any liquid effluent release.

If the denom_typ option from the options Table is 1, then: F sr = F,

Q Otherwise, if denem_typ is 2, then:

F-O " y -

R sr Fg mix Otherwise:

            *                                                                                    ~
                 .                            F F     =

R sr F +F mix

                   .                        w      dil
           .-,'              F, =        flow rate 6f undiluted waste effluent Fdil = flow rate of the dilution flow
           ,1 f.,               Rgx = mixing ratio = fraction of the release that reaches.
                 .*                      the receptor. Separate mixing ratios are st.ored for
            ,                            each pathway for each receptor.

A miring ratio of zero for a pathway receptor indicates that the pathway is not present for the receptor. The first non-zero value is used in the dose calculation. The different mixing ratios for the pathways are incorporated into the composite At factors calculated by the dose factor processing (DFP) program. ( n Also, the sem extends over all time periods s.

              . 3**$         .

2-13 Ogno h rr

1 1 Altr is available as an editable table, but can be recalculated with parameters and pathways with the Dose Factor Processing different (DFP) option. The equations used are presented in Chapter 4 of this manual. !

2.J 31 DAY PROJECTED DOSE CALCULATIONS The 31 Day Projected Dose values appear on the Standard and Special l -- Permit Reports. The Projected Dose values are calculated as follows: l D py = (D7 = p) +D at where: D pT =the 31 Day Projected Doce by organ T Dy = sum of all open release points in mrem / day by organ T when an answer of "Y" is specified for the " Update Totals" field on the release point definition screen. p =the Pro 3ection Factor which is the result of 31 divided by :: e number of days from start of the quarter to the ; end of the release.

    .               D at   = Additional Anticipated Dese for liquid releases by organ T and quarter of release.

i

        *zNOTE: The 31 day dose projections on the Approval /Results screen                          {

l

     -'              include additional

d'oses -for all units.

    . : 2. 8 POST-RELEASE PROCESSING
                                     ~

YA actual concentrations are used to check

        ..'After the release is made, 10CFR20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the start and end dates and t.imes, and is used with the volume input to calculate the release rate. Dose calculations are the same as f or the pre-release, but with actual release flow rates and rel' ease duration. l, I Setpoint calculations are not performed at the post-release stage.

          ~            ~
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e

CHAPTER 3 GAS' " JUS RELEASE CALCUIATIONS

The " annual average X/Q" method is used, in which fixed X/Q and D/Q values are used for each receptor for all dose calculations, regardless of actual wind direction and speed prevailing during a given release. Doses are calculated for each receptor location and age group specified in the Gas Receptors transaction. The controlling individual is the age group and location which receives the maximum organ dose. . 3.1 GAS PRE-RELEASE PERMIT 3 The pre-release permit .is produced by a program that uses user-

           '. entered estimates of flow rates and release times to calculate doses and activities. The dose rate from the potential release is added
           , , .to the ==v4 = nun dose rate occurring for all other releases during the
            < , duration of this releat o for "old" 10CFR20 compliance.             The noble
            #'. gas or .-tr doses and the organ doses are checked against the corresponcl.ng limits for 10CFR50 coupliance.

3.2 RADIONUCLIDE ACTIVITIES AND COMPOSITE VALUES The radionuclide results are read from one set of composite activity database records, and from three spectrum analysis result files, and saved in an activity array. If a nuclide appears in more than one spectrum, only the last value read for that nuclide is used. In case of d plication, the one not desired should be edited out of the nuclide list. The samples are read in the following order: ' ..,.~-- 3-1 - 57

1. Composite Records

2. Particulate File

3. Radiciodine File

4. Noble Gas File

The activity (Ot ) and the activity release rate (Q1 ) are calculated for each nuclide i. T. Activity Released For the plant stack and turbine building vent: 01=Ci*Vf

duration of release (min)
28316.85
Up (pCi) =(pCi/ml) (cubic feet / min) (min) (ml/ cubic feet) where:

Vf = vent flow rate in user units (usually CFM) Ci= concentration in pC1/ml Up = the flow-rate units conversion f actor which converts from user units to CFM

         'The activity release rate in yCi/see is 01=Ci    *V f

28316.85
Uy/60
For containment purge:

Qi=Ci a pump release rate (CFM)

28316.85
U y/60 A:

Qi=Qi* du:.:ation of release (min)

60 3.3 10CFR20 COMPLIANCE The maximum dose rate during the release is determined by summing together the dose rates for this release, with all concurrent releases in the database for the time of the release.

The database contains all releases for which both pre- and post-release reports have been made (the post-release program enters the data into the cumulative totals) . Pre-releases that have not been copleted, and which occur during the release under consideration, 3-2

4 k are also added into the maximum dose rate to account for releases not yet added to the cumnulative totals. 3.3a COMPLIANCE WITH OLD 10CFR20 . The three dose rates (whole body, ' skin, organ) are compared to the old 10C.TR20 limits (old anc'. new 10CFR20 are described below) as E defined i.n the Dose Limits transaction in Database Maintenance. The dose rate at or beyond the site boundary due to gaseous e.iti'2ents from the site is limited to: (a) Release rate limit for noble gases: ZK y shf I [ (X/Q) b]h < 500 mrem /yr - f *f, OR I shf I v i [Vir h) iv < 500 mrem /yr

f *f alloc s

                                                           .                      Elevated Stack a 80m Ig shf (L + 1.lM )      I    [ (X/Q)      Oh] < 3000 mrem /yr

f g
f,

           .                                                                                             l
           .                                           OR

_ Iy shf I [(L (X/Q{ + 1.1Bg) 6)g < 3000 mrem /yr

f, ' f,

        ;:                                                                       Elevated Stack e 80m
       ,. f.                                               -

where the terms are defined below. (b) Release rate limit for all radionuclides and radioactive materials in particulate form, with half lives greater than 8 days:

Ii Ip Iv W

[fp Pip mv hi ].< 1500 mrem /yr

f af alloc s where:

33 59 I

i= index over all radionuclides O v= index over all vents or stacks for the unit p= index over all pathways . r= index for receptor loc'ations E Ki= the total body dose f actor due to gamma emissions for noble gas radionuclide i, in mrem /yr per FCi/m 3, Li= the skin dose factor due to beta emissions for noble gas radionuclide 1, in mrem /yr per pCi/m 3, vir - the elevated plume gamma total body dose f actor for nuclide i at receptor location r, in mrem /yr per

                     #Ci/sec.

t i Mi= the air dose f actor due to gamma emissions for noble gas radionuclide 1, in mrad /yr per #Ci/m 3, Bir = the elevated plume gamma skin dose f actor for nuclide i at receptor location r, in mrad /yr per pCi/sec. 1.1 = mrad to mrem conversion factor in mrem / mrad - P ip = the dose f actor f or the critical organ f or nuclides other than noble gases for the inhalation pathway (in ( units of mrem /yr per pCi/m 3) and for ground plane and l 1 food pathways (in units of m2 (mrem /yr per !!Ci/sec)). ! The most restrictive age group is used.

           *     =
     ,.      fp      f actor to select which pathways are included in the
     ",'g,.
         '           calculation. Factor = 1 to include a pathway, O to exclude.

Wmv " (b)mv for tritium and the inhalation pathway and = (D/Q)mv for other nuclides and pathways. (X/Q)vr = the highest value of the annual average atmospheric dispersion factor at the site boundary, for all sectors, in sec/m 3. l l (X/Q)mv = the highest value of the annual average atmospheric dispersion factor at the distance of the site boundary, for all sectors, in sec/m 3, w

p ,- - k d ' (D /Q) my = the highest value of the annual average deposition I factor at the distance of the site boundary, for all se ctors , in m-2, {

                                                                             .              )

Oly = the average re le as ei rate of nuclide i in gaseous effluent from release point v, in pC1/sec. Noble

   .                          gases ruay be averaged over a period of 1 hour, and any
                                                                         ~

other nt2clides may be averaged over a period of 1 week. 500 = site dose rate limit for whole body in mrem / year. 3000 = site dose rate limit for skin in mrem / year 1500 = site dose rate limit for any organ in mrem / year shf = noble 9as dose shielding factor falloc= fraction of the dose limit allocated to this release - point fs = safety factor for the 'r elease point

3.3b COMPLIANCE WITH NE 10CFR20

        ., The diluted site botandary ECL ratio is compared to the lind.t!.ng
      ,( value permitted by Tech Spec:

4 . . Ciy - -

     ',                4.72 = 10             ,f* (X/Q)v        ,       ,   ,

-- . - U 0 _- 3-7 A (X/Q) , is the noble gas X/Q for the distance which matches the site boundary distance, in sec/m3 The table used I (ground-level, mixed-mode, or elevated) is specified in the release point , definition. , rp_wflow is the effluent flow rate for the 4- release point, in CFM units is the units conversion factor units = (1 m3 /35.31 ft3) - (1 min /60 sec) = 4.72 E-04 The total fraction of effluent concentration limit for the sampled mix of isotopes for the specified discharge point is given by: 1 I dp_teci = units - (X/Q) , dp_wflow

dp_uteci j

1 dp_utecl_g dp_tecl_lo = j fs

f alloc

- dp_utecl_ng units . (X/Q) , a dp_wflow w ,here: dp_tecl_hi i s ,t,b e diluted total fraction of the effluent concentration limit for the discharge point, at the site boundary, . for use in the high-gamma-activity case. ,': : dp_tecl_lo is the diluted total fraction of the effluent concentration limit for the discharge peint, at the site boundary, for use in the low-ganma-activity case. ,, dp_utecl is the undiluted total fraction of the effluent concentration limit for the discharge point. [ [zp_utecl_,g y a rp_wflowy] dp uteci g = dp_wflow l f [rp_,utecl_ng y rp_wflowy] dp_utecl_ng = dp_uteci = dp_utecl_g + dp_utecl_ng where: . dp_utecl_g is the undiluted total ECL frr.ction for gamma-esitters for the designated discharge point. dp_utecl_ng is the undiluted total ECL fraction for non-gamma-emitters for the designated discharge point, dp_utecl_g y is the undiluted total ECL fraction for gansna-emitters for the designated point v, as calculated above. . dp_utecl_ng, is the undiluted total ECL fraction for gn===-emitters for the designated point v, as calculated above. rp_wflow y is the waste flow for release point v. dp_wflow is the waste flow for the discharge point: the sum of the waste flows for

all open release points on the discharge point.

1 I .s , and the sums ext'end over all open release points v - en the discharge point. (X/Q) , is the noble gas X/Q for the distance which matches the site boundary distance, in sec/m 3. The table used (ground-level, mixed-mode, or elevated) is specified by the discharge point definition. units is the units conversion f actor units = (1 m 3/35.31 ft 3) - (1 min /60 see) = 4.72E-04 ...-- 5tho - 3-9 YS l 1 Noble Gases For the release point: If the release point setpoint equation is set to LOW ACT, then: , nratio = 1 / rp_tecl_lo h - Otherwise: . nratio = 1 / rp_tecl_hi For the ' discharge point: If the discharge point setpoint equation is set to LOW ACT, then: l ~ nratio = 1 / rp_tecl_lo Otherwise: nratio = 1 / rp_tecl_hi Radiciodines and Particulatay * 'For the release point: .' If the release point setpoint equation is set to LOW ACT,_ then: I rpratio = 1 / rp_tecl_lo f [.'Otherwise: rpratio = 1 / rp_tecl_hi For the discharge point: If the discharge point setpoint equation is set to LOW ACT, then: rpratio = 1 / dp_tecl_lo otherwise: rpratio = 1 / dp_tecl_hi ....~--- _Jhho 3-10 ; g- O 3.4b OLD 10CFR20 NRATIO i ) l The ratio of dose rate limit to dose rate . for a single release point is given below for these three cases: Noble Gases . nratio = rg = lesser of the ratios (total body dose rate limit / total body dose rate) and (skin dose rate limit / skin dose rate) ' = for a vent release, lesser of 500 mram/yr shf I gK

Qgy * (X/Q) and 3000 mrem /yr shf I (Lg + 1.1Hg) *O g

(X/Q) , = for an Elevated Stack a 80m, lesser of 500 mrem /yr .. shf I Vg

O*g and ,

3000 mrom/yr J: ~ . (X/Q) h l*E shf I ( L * + 1.1B i { i l Radiciodines and Particulates In these cases, the ratio is obtained by summing over the appropriate nuclide indices: 1500 mrem /yr rpratio = , = maxizm2m organ dose rate IPt

Ogy *Wmv

..-.' y 3-11 gy l i \ . I When the sum is over nuclides and the inhalation, ground plane and cow's milk pathways are all turned on. l 3.4c SETPOINTS . Setpoints are determined for radiation monitors on iildividual release points, and also for radiation monitors at the discharge b,- points that may combine the effluent from several release points. Calculations for the monitor response are made for noble gases, radiciodines, and particulates. For a release point, the expected monitor response to a given nuclide concentration is: - Rmon = monitor response (cpm) +B = offset + (slope

I Cg) + (quad * ( I C 1)2) +B where offset, slope, and quad are the coefficients in a quadratic fit to the monitor response to nuclide activity, and B is the monitor background.

. EMS provides an option to calculate nuclide specific responses so that Rmon is determined from the response for each nuclide, rather ~ than the sum of the nuclide concentrations, as shown above. In that ..cns e , Rmon =I ( offsett + [slopeg

Cg) + (quadt* ( Cg)2]) +B

' lThe expected response for discharge points is based on the sum of 'the erpected response for releases already in progress plus the erpected response due to release point being considered. dp E R dpmen =R +I dpmon [offseti+ slopei *C i + quad i (C d 1 )2 ) o f ( 1 where dp C = C * (F i i rp /Fdp) Cy = concentration for the release point . F rp = flow rate for the rinlease point

7. .

~ 7 dp = fl w rate for the discharge point R dpmon = discharge point monitor response for the release in progress R dpmon = the discharge monitor response before the current o release is added including the background and offsets, slopeg and quadi are the quadratic response coefficients of the discharge point monitor. . Non-isotope specific response: n = offset + slope * (ICf) + quad * (ICf)2+Rdp o

s All other equations are the same as for the individual release point, but use the discharge point monitor response and the

' discharge point allocation factor and safety factors. EMS allows for setpoint calculations based on the, standard or . ., : ' response method. Thus, each release point will have associated with p '. it, a setpoint equation: STD or RESP. This can.be set in the

Release Point (Setpoint) transaction of ' Database Maintenance.

If the release point setooint ecuation = STD : The limiting setpoint for the monitor (in pC1/ml) is given by: S m = f,

falyo,* ratio e SUM The limiting setpoint for the monitor (in user units , e.g. , cpm) is given by:

( ..+. . SUm =f s *falloc

ratio * (Phon - B) +B where offset = 1. noble gas offset factor .

2. radiciodine offset factor '

3. particulate off se't factor slope = 1. noble gas slope factor

2. radiciodine slope factor

3. particulate slope f actor quad = 1. noble gas quadratic factor

2. radioiodine quadratic factor

3. particulate quadratic factor f3 = safety factor'for the release point falloc = dose rate allocation factor for the release point i 1

ratio = 1. nratio for noble gases

2. rpratio for radioiodines

3. ,rpratio for particulates SUM = 1. I noble gas concentrations, for nob:.c gases

2. I radiciodine concentrations, for radiciodines

3. I particulate concentrations, for particulates

,- Pton = 1. noble gas monitor response - 2. radioioliine monitor response

3. particulate monitor response (

.[* B = 1. observed background response for the noble gas h'. monitor

2. . observed background response for the radiciodine monitor

3. observed background response for the particulate monitor NOTE : Separate calculations are made for noble gases, radiciodine, and particulates The limiting setpoint for gaseous releases is determined separately for noble gases, radiciodines, 'and particulates for each release point and discharge point.

~ ' q t If the release point setpoint ecuation = RESP : The reported setpoint for the monitor (in pCi/ml) now becomes: S ,gx = [mrtol * (SUM - B)) + (mrtolb

B) ,

The limiting setpoint f or the monitor (in user units, e.g. , cpm) now becomes: SU ,,x = [mrtol * (Rmon - B) ] + (artolb

B)

I where mrtol = 1. ' monitor response tolerance factor (noble gas)

2. monitor response tolerance factor (radiciodine)

3. monitor response tolerance factor (particulate)

SUM = as defined above ( - B = as defined above ~ mrtolb = 1. monitor tolerance background factor (noble gas)

2. monitor tolerance background factor

* (radiciodine) - 3. monitor tolerance background factor ; (particulate) . l' Rmon = as defined above 3.4d REPORTED SETPOINTS If the release. point setpoint equation is STD, then the maximum ,setpoint is compared with the response and default setpoints. NOTE :The response setpoint as defined in this section is not necessarily the same as the maximum setpoint based on the RESP setpoint equation, as defined in the previous section. S response is defined below. -+ 3-15 2na yg 7/ ; The reported setpoint is as follows:

1. Reported = S response if Sresponse < Smax < Sdefault OR if Sdefault < Sresponse < S max

l

2. Reported = S max

) if 3 response 1 S max

3. Reported = Sdefault !

if Sresponse < Sdefault < Smax where Sg- = as defined in the previous section 1 r mrtol

SUM [pci/ml] l S response " I l

t. [mrtol * (Rmon - B) ] + (mrtolb

B) [ User l Units)

Sdefault = normal setpoint defined for the release point in units of [pCi/ml] and [ User Units). . NOTE : Separate checks are made for each setpoint in [pCi/ml] and (User Units) for the noble gas, radiciodine, and particulate ; l monitors. y ... 3.5 MAXIMUM WASTE FLOW .The maximum waste flow calculation is based on what the WFLOW M ,_ ','(<' ; option(release point setpoint calculation option) is set to. This option can take on one of three values: NONE, DOSE, and CALC. Gaseous release point setpoint WFLOW M can be set to either NONE or DCSE. For gaseous releases, Wmax = the min 4m"m of Q 3 and Rcwmax where Q = Release point maximum waste flow rate as stored in the release point definition 3-16 l ) l If WFLOW M option = NONE R ewmax = waste flow rate for the sample, Vg If WFLOW M option = DOSE fs

Yf

^*"t10.* Rewmar " F wsfac where - f, = Safety f actor for the release point nratio = nratio as described in section 3.4 (i . e . , 3.4a & 3.4b) Vf = Waste flow rate for the release (sample) . F,,gge = Waste flow rate DOSE setpoint safety factor 3.6 DOSE RATE AND CUMUIATIVE DOSE CALCULATIONS Noble Gas Total Body Dose Rate Calculations 'The total body dose rate due to gamma emissions by noble gas I releases from vent v is calculated by using the following -l . expressions: Dt = 1.14

10~4 (shf) (X/Q) , I (K i*bgy) Vent < 80m

. i 'Dt = 1.14

10~4 (shf) I (Vi *bgy) Elevated Stack = 80m i

where: Dt= the total body dose rate due to gamma emissions by noble gas releases from vent v, in mrem /h. 1.14

10-4 = inverse of the number of hours in a year.

O ..,,- ,_ w 73 1 l l Noble Gas Dose Calculations The dose contribution due to noble gases in gaseous effluents is calculated using the following expressions: For any time period, for air dose due to ganna radiation: , ~ D = 3.17

10 ZM i *

(X/Q) v

Qiv Vent < 80m

. y OR ~ D = 3.17

10 IB *O h Elevated Stack n 80m h

and for air dose due to beta radiation: ~ D = 3.17

10 ZN
Vent < 80m p i -(X/Q)v
Qiv OR

~ D = 3.17 a 10

IN * (X/Q) v
Q Elevated Stack n 80m p i iv .

1 and for total body dose: i shf a f *o I Kg * (X/Q)y *- Ogy Dt" - Vent < 80m - ) (5.256E+05/ duration) OR shf a fe o ZVir

Oiv Elevated Stack a 80m Dt=

/ ** (5.256E+05 / duration) ' and for skin dose:

l shf a fe o Z (Li + 1.1Mg) (X/Q)y *Qiy D s= Vent < 8.0m (5.25 6E+05/ duration)

OR shf

f o* I [ (Li* (X/Q)y) + 1.1Bir)3
O iv D s= Elevated (5.25 6E+05/ duration) Stack a 80m i 3-18 79

4 where: D y= the total gamma air dose from gaseous effluents, in , mrad. , Dp = the total beta air dose from gaseous effluents, in _- mrad. Dt= the total body dose from gaseous effluents, in mram. D3 = the total skin dose from gaseous effluents, in mrem. 3.1-

10-8 = inverse of number of seconds in a year 5.256E+05 = number of minutes in a year fo = The occupancy factor defined for the receptor at the given location, a dimensionless number s 1.0 ,

Ki = the total body dose factor due to gassna emissions for noble gas radionuclide i, in mrom/yr per pCi/m 3 , Li= the skin dose f actor due to beta emissions for noble gas radionuclide i, in mrem /yr per pCi/m 3. Q 5 Mi= the air doWe f actor due to gn=rna emissions for noble gas radionuclide i, in mead /yr per pCi/m 3. '* I Ni= the air dose factor due to beta emissions for noble gas radionuclide i, in arad/yr per pCi/m 3. Vi= the gamma total body dose f actor for nuclide i at receptor location r, in mrem /yr per pCi/sec. , By = the gamma skin dose factor for nuclide i at receptor location r, in mrem /yr per pCi/sec. (X/Q), = the highest value of the annual average atmospheric dispersion factor for vent or stack v at the site boundary, for all sectors, in sec/m 3. O O ..:- . g ' Ogy = the release of noble gas radionuclides, i, in gaseous effluents from vent or stack v in pCi. Releases are cumulative over the time period selected for the report. Ogy = the release rate of noble gas radionuclides, i, in . gaseous ef fluents from vent or stack v in' pCi/sec. Release rates are c'umulative over the time period selected for the report. ~ duration = the duration of the release in minutes . Orean Dose Calculations For any time period, organ doses from particulates and iodines are: D Ta = 3.17

10-8 . f .o I RipTa
Wpv *Qv i where:

3.17 a 10~8 = inverse of number of seconds in a year DTa = the cumulative dose for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents, in mrem. R ipfa = the dose f actor for each radionuclide i, pathway p, y_ 2 (mrem /yr) per pCi/sec organ T, and age group a, in m .E or mrem /yr per pCi/m 3, Wpy = the annual average dispersion parameter for estimating the des = to an individual at the critical ' g. location, as appropriate to pathway p and release point v, is shown below:

1) (X/Q), in sec/m3 , for the inhalation pathway and f or tritium and C-14 in all pathways.

2) (D/Q) for the food and ground plane pathways, in metezs3 Qy i

= the release of nuclide i in gaseous effluents from release point v. Releases are cumulative over the time period selected for the report. Only tritium, I-131, I-133, and radiciodines in particulate form with half-lives greater than 8 days are included. 3-20~ % l ~ 13 Q The marimum exposed individual is determined by the maximum dose received by any organ. The summation extends over all applicable nuclides and pathways. . I 3.7 RESOLVING DOUBLE-COUNTING OF DOSE AND ACTIVITY , Gaseous release points fall into three categories for double- ~ counting of dose and activity. One, a release point will not have activity sampled twice. Two, a release point can have activity that is sampled again downstream and would be double-counted if no corrections were applied. Three, a release point can have samples containing activity already sampled once upstream which would be double-counted if no corrections were applied. The last two categories can be called the "CAUSE" release point and the "EFFECT" release point, respectively. To avoid double-counting dose and activity, only the "EFFECT" release point will have its activity and concentrations corrected as follows. Corrected activity is calculated as follows: ] A c,g ='A,i - Act Ae g =the corrected "EFFECT" release point activity for - nuclide i which defaults to zero if its value is less than zero. .?- A,g =the initial "EFFECT" release point activity for nuclide i , A ct =the "CAUSE" release point activity for nuclide i ' Corrected concentrations are calculated as follows: / l Ci=c (Ae t / V,) = 35.315 where: Ceci =the corrected "EFFECT" release point concentrations for nuclide i V, = the waste volume for the "EFFECT" release point 35.315 = conversion f actor from Ci/f t 3 to uCi/ml (Ci/ft 3

O ft3 /1728 in 3
in /16.387 3

cm3) Y . . . ... 1 3-21 NO_ . ru O 3.8 31 DAY PROJECTED DOSE CALCULATIONS The 31 Day Projected Dose values appear on the Standard and Special Permit Reports. The Projected Dose values are calculated as , follows: . -. D py = (DT

p) +D ar where:

D pt =the 31 Day Projected Dose by organ T D7 = sum of all open reiease points in mrem / day by organ T when an answer of "Y" is specified for the'" Update Totals" field'on the release point definition screen. p =the Projection Factor which is the result of 31 divided by the number of days from the start of the quarter to the end of the release. Dai = Additional Anticipated Dose for gaseous releases by organ T and quarter of release. I NOTE: The 31 day dose projections on the Approval /Results screen include additional doses for all units. GAS POST-RELEASE PROCESSING . . f"3 . 9 - Af ter a pre-release permit has been approved, the post-release program is run to: ,h. o Enter actt.al release start and stop times, flow rates, etc. o Check 10CFR20 limits o Check 10CFR50 limits o Add the dose and activity data into the cumulative totals. Compliance with 10CFR20 limits is checked in the same way as described for the pre-release program. Dose rates are calculated and compared to 10CFR20 limits. Monitor setpoints are not calculated at the post release stage. l l 3-22 q ~ %J 7 CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS The DFP option is used to calculate the liquid dose factors j described previously. Dose factors are calculated separately for j each nuclide, organ, and age group. The age group, applied to a l specific receptor's dose calculations, is part of the receptor 4 specification. For a particular receptor, the total dose factor (AiTr) is a sum over each pathway p with its specific mixing ratio: A = IR A iTr R mixe reP if,r,p .- mix,r s ..* ', ' where , .,: Air,r,p = the dose f actor for nuclide i, organ T, receptor age A: group r, and pathway p '

l Rmix,r,p = mixing ratio for the pathway I Pd x,r = mixing ratio for the receptor, which is the first non-zero value of R mix,r,p encountered during the calculation The user specifies which pathways are included by setting the mixing j ratios f or the pathways desired to the correct non-zero value. If the receptor mixing ratio for a given pathway is zero, that term is i not included in the sum.

1 4-1 m 79 5 3 The DFP option of EMS uses a more expanded form for liquid dose factors than is given in NUREG-0133. These equations are taken from R.G. 1.109, and account for nuclide decay as well as shoreline doses. If desired, parameters may be selected to reduce the calculations to match NUREG-0133 e::actly. Four different forms of equations are used for the dose factors. h 4.1 POTABLE WATER The dose factor for potable water is: Air,r,p = k o . (Ur ,p /dw)

Ng
DFif,r * * (~ Aipt )

where - Air,r,p = dose parameter f or organ T, for the receptor age group r, for nuclide i, due to exposure pathway p, in mrem /hr per pCi/ml ko = units conversion f actor, = 1.142E5 = 1E6 (pCi/pCi)

1000 (ml/Kg) / 8760 hr/yr Ur ,p =

~ usage factor for pathway p and age group r O dw = additional dilution f actor for potable water Ni = fraction of the radionuclide activity released to 9 the water' discharge path that reaches a specific receptor. DFiT,r = ingestion dose conversion f actor for nuclide i for ,3 ' recep or age group r in organ T, in mrem /pci (Tables E-7 to E-11 of R.G. 1.109) Ag= decay constant for nuclide i tp= average transit time in seconds 4.2 AQUATIC FOODS PATHWAYS The liquid dose factor is .,a Alf,r,p = k o

Ur ,p
BFg,p
Ni
DFif, r
eXP (- A ti p) 4-2

(v5 where BF i,p= bioaccumulation f actor f or pathway p and nuclidu i (from Reg. Guide 1.109, Table A-1). Other variables are as defined on the previous page. , l ~~. ~ 4.3 SHORELINE RECREATION PATHWAY The pathway-specific dose factors for shoreline deposition are given by. ~ 1-e ib . A =k W N U a s i f,r,p e i sd DFG if it , r, p y i where p W, = shoreline width factor G . k, = conversion factor = k e *k e a mtv/3600 ke = water to sediment transfer coefficient in L/kg hr ~ mtv ' = Mass density of sediment in kg/m 2 , 40 , kg/m2 j / 3600 = Seconds per hour units conversion 4: factor tb = length of time sediment is exposed ' to contaminated water, 4.716EB sec t sd = transit time to deposit activity on shoreline DFGiT = the dose conversion factor for standing on ground contaminated with nuclide i, in mrem /hr per pCi/m2 ~ . . P-- . 4.4 IRRIGATED VEGETABLE PATHWAY A = 1.14

10
U CF g
DF where:

1.14 = 105 = a units conversion f actor CFiy = the concentration f actor for radionuclide i in irrigated vegetables, as applicable to the vicinity of the plant site (pCi/kg) / (pCi/L) . Calculation of the Concentration Factor The calcuiation of the concentration f actor for radionuclide i in irrigated vegetables, CFly as used in the equation for A17, is calculated as follows for all radionuclides other than Tritium: ' ~ -A t ib ~* I iv( t CFi , = N *M*I r (1 - e *) , i. YA y Ei' i For Tritium, the equation is as follows: CFgy =Ni*M*L y . uhere , [- M = the additional dilution factor from the near '(, field' of the discharge structure to the point of irrigation water usage. I = the average irrigation rate during the growing season (L/m2 h). - r = the fraction of irrigation-deposited activity retained on the edible portions of leafy vegetables. There are separate values available for radiciodines and particulates. Y, = the agricultural productivity of irrigated leafy vegetables (kg/m 2), J ~ ~"~ l I 1 , i fy = the fraction of the year that vegetables are irrigated. Egy = the crop to soil concentration factor applicable to radionuclide 1 (pCi/kg vegetables) / (pC1/kg soil) . . P = the effective ' surface density of soil' (kgh32). E' 1 1 = the decay constant for radionuclide 1 (h-1) . AEi = the effective removal rate for activity deposited on crop leaves (h-1) , calculated as AEi " Ai+Aw 2, = the rate constant for removal of activity from plant leaves by weathering (h-1) . = t, the period of leafy vegetable exposure during the growing season (h). tb = ' the period of long-term buildup of activity in soil (h). = th the time between harvest of vegetable and human consumption (h). Ly = the water content of leafy vegetable edible parts (L/kg). .y . . . 4.5 REDUCTION TO NUREG-0133 EQUATIONS 'g,NUREG-0133 does not have shoreline deposit equations, which can be ',sliminated by setting the Water Recreation Mixing Ratio to zero in the Liquid Receptor Transaction definition under EMS. For the other equations, reduction to NUREG-0133 is obtained by setting: Ni= 1 (this can be set in the definition of Fraction of Activity Reaching Receptor'in DFP) average transit time t = 0 (t his can be set in the ~ definition of Dose Calculation Parameters in DFP) O . p r3 4-5 O b CHAPTER 5 GAS DOSE FACTOR CALCULATIONS The DTP option is used to calculate the gas dose f actors described previously. Dose factors are calculated separately for each nuclide, organ, and age group. The age group, applied to a specific receptor's dose calculations, is part of the receptor specification. The same gas dose factors are used for both the site boundary dose rate calculations and for the maximum individual controlling location dose calculation. , The dose factor for each particulate or iodine nuclide 1 (or - tritium) is given below. It i.s a function of pathway, organ, and age group. The pathways considered are: y 1. Inhalation , l

2. Ground

3. Milk (Cow or Goat)

4. Meat

5. Vegetable 5.1 INHALATION PATHWAY Pit a = K' (BR) , (DFAiTl a (mrem /yr per #Ci/m3)

K' = 1E6 pCi/pCi ~ O (BR), = breathing rate for age group a, in cubic m/yr 1 (DFA T)a = inhalation dose f actor for organ T, for age group a, for nuclide i, in mrem /pCi , *~. - 5.2 GROUND PLANE PATHWAY j Rita = K' K" (SF) DFGgy [ (1 - e~d i t) /j (m2 -mrem /yr per pCi/sec) where K' = lE6'pCi/pCi l K" = 8760 hr/yr Ag= decay constant for nuclide 1, in sec-1 t= exposure time (sec) = 4.73E8 (15 years) , DFG if = ground plane conversion f actor for nuclide i, organt The (The same DFGiT factors apply to all age groups. f actors labelled total body in the database are ,- applied to all other organs) SF = shielding factor . l* .' o* ")**5.3 .; MILK PATHWAY Rita = K' (DniTI a *- (tfOF F ,1 U ,p * -(A +1 )t -A t - r (1-e i w e) (1 - e i b) ff + B h Ps y (; .y) w Pj i - p Os ...P- . 5-2 'r (1-e ~ i w t,) gi , ,4 tg b) ' + (1-f f )e ih +B Y, (Ag + A,) pA t (m2 - mrem /yr per pCi/sec) where K' = 1E6 pCi/pCi *07= feed consumption rate by the milk animal (cow or goat) (Kg/ day) U ap = age group a milk consumption (cow or goat) Y p = agricultural productivity by unit area of pasture feed grass, in Kg/sq. m Ys = agricultural productivity by unit area of stored feed, in Kg/sq. m Fmi = stable element transfer coefficient for nuclide i, frein feed to milk, in days / liter B iy = f actor for uptake of radionuclides from soil by crops r= fraction of deposited activity retained on animal feed grass (cow or milk). Separate values are used for .' radiciodines 'than all other particulates. (DFLig ),3 = ingestion dose f actor for organ T, for nuclide 1, for receptor in age group a, in mrem /pCi At= decay constant for nuclide i Aw = decay constant for removal of activity on leaf and plant surfaces by weathering, in sec-1 tg = transport time from pasture to cow or goat to milk to receptor, in sec. th= transport time from pasture to harvest to cow or goat to milk to receptor, in sec. t,= seasonal crop exposure time, in sec. fp = fraction of year that animal is on pasture 5-3 ~ O f,= f raction of animal feed that is pasture grass while animal is on pasture Carbon-14 in Milk ) , = K' K" ' Fd OF Uap (DFLiTI a Pc (0.11/0.16) e ~ Ai t'f ~~* -. Rita (m2 -mram/yr per pCi/sec) where K"' = 1E3 gm/Kg ~ pc = fractional equilibrium ratio 0.11 = fraction of total plant mass that is natural carbon 0.16 = concentration of natural carbon in the atmosphere (g/m3) and' all other parameters as defined above n . Only Op and U ,p depend on cow or goat. l ... Tritium in Milk * ~N 3 :, RiTa = K'K"' Tmi O F Uap (DFLgy), * (0.75) (0.5/B) etif (m2 -mrem /yr per pCi/sec) , where . K"' = 1E3 gm/Kg H= absolute humidity, gm/ cubic meter 0.75 = fraction of total feed that is water 0.5 = ratio of specific activity of feed grass water to the atmospheric water and all other parameters as defined above H i e Only 07 and U,p depend on cow or goat. 5.4 MEAT PATHWAY . R iTa = K' (DFLit) a e if0 F7 fi ap U * ~ ~ r (1-e' i w e) 1-e ib ff +B Y p (A1 + A,) P At . -(A +A )t -A t - r ( 1-e i w e) 1-e ib . + (1-f f )e ;i h +B iv Ps y (2 y) p j . i where Ffi = stable element transfer coefficient fo2 nuclide i, from feed to meat, in days /Kg U,p = receptor's meat consunption (Kg/yr) th= transport time from crop field to receptor, in sec tg = transport time from pasture to receptor, in sec l ,.', and all other f actors are as described for the cow-milk pathway , 4 Carbon-14 in Meat Rit a = K' K"' F fi Op U ap (DFLitl a Pc (0.11/ 0.16) e -A tlf (m2 -mrem /yr per pCi/sec) where all terms are as defined above. ..-<-- u 5-5 ( i . Tritium in Heat R ifa = K' K" ' F ft QFUap (DFLiTl a * (0.75) (0.5/H) e ~A tif (m2 -mrem /yr per pCi/sec) where all terms are as defined above.- , ' -~ . 5'. 5 VEGETABLE PATHWAY R = K' U f e iL

iTa (DFLiT)a a L o

~ ~" ~ r (1-e i w e) Bg (1-e i b) l Y y (Ag + A,) P At . +U f e' i s

b b ~ ~

r (1-e i w e) Bh (1-e i b) Y (Ai + Aw) pA sv i - . 1 (m2 mrom/yr per pC1/sec) '[<where UI = consumption rate of fresh leafy vegetation for age group a, in Kg/yr US= consumption rate of stored vegetation for age group a, in Kg/yr f3= fraction of annual intake ci leafy vegetation grown locally fg =* fraction of annual intake of stored vegetation grown locally O . .- . 4 1 l tn = average time between harvest of leafy vegetation and consumption, in sec. ) i t s= average time between harvest of stored vegetation and ' consumption, in sec. I ~ tb= long term sediment erposure time, in sec. t,= seasonal crop erposure time, in sec. b Yy = vegetation areal density, in Kg/m2 Y sv = stored vegetation areal density, in KG/m2 p= effective soil surface density . Biy.= soil to vegetation transfer f actor for nuclide i All other f actors are as defined above. Carbon-14 in Veaetables RiT a = K' K"' (Oh+U() (DFLiT)'a Pc (0.11/0.16) e -A tif (m2 -mrem /yr per pC1/sec) where all variables are as defined earlier. Tritium in Veoetables Rit a = K' K" ' (Uk+ Uf) (DFLiTl a * (0.75) (0.5/B) e -A if t (m2 -mrem /yr per pCi/sec) where all variables are as defined earlier. 5.6 REDUCTION TO NUREG-0133 EQUATIONS Inhalation and ground plane pathways are the same in R.G. 1.109 and NUREG-0133. For the other pathways (milk, meat, and veget able) , these equations reduce to the NUREG-0133 values by setting: tb=0 .:a

4

~ . I l l t, = 9. 999g19 i tf=0 (in tritium equations only) l There are no C-14 equations in NUREG-0133, which can be obtained by , setting pc = 0. .

~ .

~ l e e . 8 5 / . e i 1 ' W, 1 . .-A " . c l -l 5-8 ; I O 7 APPENDIX A REFERENCES 9

1. Boegl1, J.S., R.R. Bellamy, W.L. Britz, and R.L.

Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclea'r Power Plants, "NUREG-0133" ' (October 1978).

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, U.S. NRC Regulatory Guide

~ l .109, Rev. 1 (OcEober 1977). .'o / i i . . := A-1 CQ Q\ i I c--_ . . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ O Appendix X, Rev.18, was not distributed to controlled copy holders of the ODCM. Appendix X is available in RMD. O i l 1 l O O Appendix Y, Rev.18, was not distributed to controlled copy holders of the ODCM. Appendix Y is available in RMD. O l O}}

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5.0 REFERENCES

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1.0 INTRODUCTION

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1.0 INTRODUCTION

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1.0 INTRODUCTION

1.1 Background

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