ML20082L804

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Rev 10 to ODCM
ML20082L804
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 04/04/1991
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20082L795 List:
References
PROC-910404, NUDOCS 9109040372
Download: ML20082L804 (14)
v • d • e


Text

. _ .

VERMoliT YA!EEE liUCLEAR POWER STATIC!i OFF-SITE DOSE CALCULATIOlt MANUAL REV. # 10 Reviewed ( b ' ? I M,

/ 3 b 5'[# /

Plant p rations Review Committeb u Approved ._A .. J /

Plant Manager Approved / // b , k / Nf~ 9/

V1'c ?redidpr,rknd Manager of eratioh) y 9109040372 910829 PDR ADOCK 00000271 R PDR

1.0 INTRODUCTION

This ODCM (Off-Site Dose Calculation Manual) provides formal and approved methods for the calculatich of off-site concentration, off-site doses, and effluent monitor setpoints in order to comply with the Vermont Yankee Technical Specifications 348/4.8 and 3.9/4.9, hereafer referred to as the Radiological Efflus t Technical Specifications. The ODCM forms tne basis for plant procedures an, is designed for use by the procedure writer. In addition, the ODCM will s.s useful to the writer of periodic reports required

I by the NRC on the dose consequences of plant operation. The methods contained herein follow accept 2d NRC guidance (Regulatory Guide 1.109) unless otherwise

, noted in the text.

It shall be the responsibility of the Chemistry Supervisor and Radiation Protection Supervisor to ensure that the ODCM is used in the performance of the surveillance requirements of the appropriate portions of Technical Specifications. The administration of the program for the disposal of slightly contaminated septic waste, as described in Appendix B, is the responsibility of the Senior Environmental Program Manager.

All changes to the ODCM must be reviewed by PORC ar.d approved by MOO, in accordance with Technical Specification 6.13, prior to implementation. All approved changes shall be submitted to the NRC for their information in the Semiannual Radioactive Effluent Report for the period in which the change (s) was made effective. The plant's Document Control Center (DCC) shall maintain the current version of the ODCM and issue under controlled distribution all approved changes to it.

I I

I Revision 10 Date 4/4/01 1-1 5713R/20.74

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4.0 ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring stations are listed in Table 4.1. The locations of the stations with respect to the Vermont Yankee plant are shown on the maps in Figures 4-1 to 4-6.

I 4.1 Intercomparison Projram All routine radiological analyses for environmental samples are performed at the Yankee Atomic Environmental Laboratory (YAEL). The YAEL l

! participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for all apppropriate species and matrices offered by the agency.

4.2 Airborne Pathway Monitoring The environmental sampling program is designed to achieve several major' l objectives, including sampling air in predominant up-valley and down-valley wind directions, and sampling air in nearby communities and at a proper control location, while maintaining continuity with two years of preoperational data and 18 years of operational data (as of 1990). The chosen l air sampling locations are discussed below.

To assure tht.5 an unnecessarily frequent relocation of samplers will not be required due to short-term or annual fluctuations in meteorology, thus incurring needless expense and destroying the continuity of the program, long term, site specific ground level D/Qs (five-year averages - 1978 through 10BU were evaluated in comparison to the existing air monitoring locations to determine their adequacy in meeting the above-stated objectives of the program and the intent of the NRC general guidance. The long-term average meteorological data base precludes the need for an annual re-evaluation of air sampling locations based on a single year's meteorological history.

Revision 10 Date 4/4/91 41

$713R/20.74

h h Table 4.1 a Radiological Environmental Monitoring Stations (l)

Exposure Pathway Sample Location and/or Sample and Designated Code (2) Distan$e (km)(6 Direction (6)

1. AIRBORNE (Radiotodine and Particulate)

AP/CF-11 River Station 1.9 SSE No. 3.3

-I AP/CF-12 N. Hinsdale, NH 3.6 NNW AP/CF-13 Hinsdale Substation 3.1 E AP/CF-14 Northfield, MA 11.3 SSE

_I AP/CF-1S Tyler Hill Road (4) 3.2 WNW AP/CF-21 Spofford Lake 16.1 NNE

2. WATERBORNE
a. Surface WR-11 River Station 1.9 Downriver l WR-21 No. 3.3 Rt. 9 Bridge 12.8 Upriver Plant Well i b. Ground WG-11 WG-12 WG-22 Vernon Nursing Well Skibntowsky Well 2.0 14.3 On-Site SSE N I
c. Sediment SE-11 Shoreline Downriver 0.8 On-Site from SE-12 North Storm 0.1S On-Site Shoreline Drain Outfa11(3) i 3. INGESTION
a. Hilk TM-11 Miller Fatm(4) 0.8 WNW TM-12 Dominick (D) 5.2 E TM-13 Newton Farm 5.1 SSE TM-14 Brown Farm 2.6 S I TM-16 TM-24 Tall Oaks Farm County Farm 4.7 22.S WNW N l l b. Mixed Grasses TG-11 River Station No. 3.3 1.9 SSE TG-12 N. Hinsdale, NH 3.6 NNE TG-13 Hinsdale Substation 3.1 E TG-14 Northfl+1d, MA 11.3 SSE TG-15 Tyler n111 Rd,(4) 3.2 WNW TG-21 Spofford Lake 16.1 NNE Revision 10 Date */4/91 4-2 S713R/20.74

Table 4.1 (continued) 1 Radiological _ Environmental Monitoring Stations (I) i Exposure Pathway Sample Location Distance and/or Sample and Designated Code (2) (km)(6) Direction (6)

c. Silage TC-ll Hiller Farm (4) 0.8 WNW TC-12 Dominick (5) 5.2 E TC-13 Newton Farm S.1 SSE TC-14 Brown Farm 2.6 S TC-16 Tall Oaks Farm 4.7 WNW TC-24 County farm 22.5 N l
d. Fish FH-ll Vernon Pond -- On-Site FH-21 Rt. 9 Bridge 12.8 Upriver
4. DIRECT RADIATION OR-1 River Station 1.6 SSE No. 3.3 DR-2 N. Hinsdale, NH 3.9 NNW ,

DR-3 Hinsdale Substation 3.0 E DR-4 Northfield, MA li.0 SSE DR-5 Spofford Lake 16.3 NNE OR-6 Vernon School 0.46 WSW OR-7 Site Boundary 0.27 W DR-8 Site Boundary 0.25 SW DR-9 Inner Ring 2.1 N DR-10 Outer Ring 4.6 N OR-il Inner Ring 2.0 NNE OR-12 Outer Ring 3.6 NNE OR-13 Inner Ring 1.4 NE DR-14 Outer Ring 4.3 NE OR-15 Inner Ring 1.4 ENE OR-16 Outer Ring 2.9 ENE DR-17 Inner Ring 1.2 E DR-18 Outer Ring 3.0 E DR-19 Inner Ring 3.5 ESE OR-20 Outer Ring 5.3 ESE DR-21 Inner Ring 1.8 SE DR-22 Outer Ring 3.2 SE OR-23 Inner Ring 1.8 SSE OR-24 Outer Ring 3.9 SSE DR-25 Inner Ring 2.0 S Revision 10 Date 4/4/91 4-2a 5713R/20.74

F' L table 4.1 (continued)

[ Radiological Environmental Monitoring Stations (l) sample Location

{ Exposure Pathway and/or Sample and Designated Code (2)

Distance (km)(6) Direction (6) s OR-26 Outer Ring 3.7 5 DR-27 Inner Ring 1.0 SSW 1 OR-28 Outer Ring 2.2 SSW DR-29 Inner Ring 0.7 WSW DR-30 Outer Ring 2.3 I DR-31 DR-32 Inner Ring Outer Ring 0.8 5.0 SW W

WSW

's OR-33 Inner Ring 0.9 WNW g OR-34 Outer Ring 4.9 W DR-35 Inner Ring 1.4 WNW DR-36 Outer Ring 4.7 WNW Inner Ring I DR-37 DR-38 Outer Ring 3.0 7.7 NW NW OR-39 Inner Ring 3.2 NNW OR-40 Outer Ring 5.8 NNW -

1 (1) Sample locations are shown on Figures 4.1 to 4.6.

(2)

I Station IXs are indicator stations and Station 2Xs are control stations (for all but the direct radiation stations).

(3) To be sampled and analyzed semiannually.

(4) Non-Tech Spec station.

l (5) Non-Tech Spec station. Sample will be collected as available.

(6) Distance and direction from the center of the Turbine Building for l direct radiation monitors; from the plant stack for all others.

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Revision 10 Date 4/4/91 4-3 5713R/20.74

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APPENDIX 1 RADIDACTIVE LIQUID, GASEOUS. AND SOLID WASTE TRFXIMENT SYSTDiS I licquirement : Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Connission in the Sciciannual Radioactive Effluent Release Report for the period in which the I evaluation was reviewed by the Plc.nt Operation Review Connittee.

licspouse: There were no licensee initiated major changes to the radioactive waste systems (11guld, gaseous, and solid) during this reporting period.

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lI il II I-1 8851R

APP!WDIX J ON-SITE DISPOSAL OF SEPTIC WASTE f

Requirement: Off-Site Dose Calculational Manual, Appendix li requires that the dose irnpact due to on-site disposal of septic waste during the reporting year and from previous years be reported to the Convoission in the Semiannual Radioactive Ef fluent Report filed after January 1. If disposals occur during the reporting year.

se., _ , mo ..s,..se is ,. 1,ed fo, t,,,s .. o,ti,,, ,e m e.

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