ML20246P328
| ML20246P328 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/31/1988 |
| From: | Amaro C, Bohn T, Serrano W EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20246P255 | List: |
| References | |
| CON-FIN-D-6034 EGG-PHY-8052, NUDOCS 8909110087 | |
| Download: ML20246P328 (24) | |
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PDR ADOCK 05000271 WE?hS&WOh50
o EGG-PHY 8052 TECHNICAL EVALUATION REPORT for the EVALUATION OF ODCM UPDATED THROUGH REVISION 4 VERMONT YANKEE NUCLEAR POWER STATION NRC Docket NO. 50-271 NRC LICENSE NO. OPR-28 T. S. Bohn W. Serrano C. R. Amaro M. R. Winberg Published May 1988 1.
Idaho National Engineering Laboratory EG&G Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. 06034
_.___________._______________.______________i
ABSTRACT
.The Offsite Dose Calculation Manual for the Vermont Yankee Nuclear Power Station (VYNP) contains current methodology and parameters used in the calculation of offsite doses due to radioactive liquid and gaseous i
effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the execution of the' environmental
]
radiological monitoring program. Revision 0, dated March 5, 1984 was submitted to the NRC and subsequent Revisions 1, 2, and 3 were reported to the NRC in the Semiannual Effluent Report for July-December 1986. The latest revision, Revision 4, was reported to the NRC in the Semiannual Effluent Report for July-December 1987. The NRC transmitted Revision 0-along with Revisions 1, through 4, to the Idaho National. Engineering Laboratory (INEL) for review. The ODCM updated through Revision 4 was reviewed in its entirety by EG&G Idaho at the INEL and the results'of the review are presented in thf5 report.
It was determined that the ODCM updated through Revision 4 uses methods that are, in general, in agreement with the guidelines of NUREG-0133. However, it is recommended that another revision to the ODCM be submitted to address the discrepancies identified in the review.
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FOREWORD This report is submitted as partial fulfillment of the " Review of Radiological Issues" project being contracted by the Idaho National Engineering Laboratory for the U. S. Nuclear Regulatory Commission, Office of Nuclear -Reactor Regulation. The U. S. Nuclear Regulatory Commission funded'the work under FIN 06034 and NRC B&R Number 20 19 05 03.
This report was prepared as an account of work sponsored by an agency of the United States Government..Neither the United States Government nor any agency thereof, nor any of their employees, makes any warrant, expressed or implied, or assumes any legal liability or responsibility for any third party's-use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately-owned rights.
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1 CONTENTS 1
Page j
i 1
Abstract............................
i Foreword............................
11 1.
Introduction........................
I 2.
Review Criteria.......................
2 3.
Evaluation.........................
3 4.
Conclusions.........................
15 5.
References..........
18 iii i
J 1.
INTRODUCTION I
Puroose of Review This document reports the review and evaluation through the latest version, Revision 4, of the Offsite Dose Calculation Manual (00CM) submitted by the Vermont Yankee Nuclear Power Corporation (VYNPC), the Licensee for the Vermont Yankee Nuclear Power Station (VYNP). The ODCM'is a supplementary document for implementing the Radiological Effluent l-Technical Specifications (RETS) in compliance with 10 CFR 50, Appendix I requirements.Ill l
Plant-Soecific Backoround VYNPC submitted an ODCM for VYNP with letter dated January 23, 1984 to the Nuclear Regulatory Commission (NRC). The NRC reviewed the ODCM and found it to be generally acceptable.as stated in letter dated October 9, 1984.[2]
In the interim, another ODCM identified as Revision 0, dated March 5, 1984 was submitted to the NRC with letter dated March 5, 1984.[3]
Subsequent changes identified in Revisions 1, 2 and 3 were reported to the NRC in the Semiannual Effluent Report 'for the second half of 1986.I43 The latest revision, Revision 4, was reported to the NRC in the Semiannual Effluent Report for July-December 1987.[5] The ODCM, updated through Revision 4, was submitted by the NRC to an independent review team at the Idaho National Engineering Laboratory (INEL). The INEL team reviewed the ODCM in its entirety and the results and conclusions are presented in this report.
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2.
REVIEW CRITERIA j
Review criteria for the ODCM were provided by the NRC in two documents:
l NUREG-0473, RETS for Boiling Water Reactors (BWRs)[6]
NUREG-0133, Preparation of RETS for Nuclear Power PlantsI73 The following NRC guidelines were also used in the ODCM review:
" General Centents of the Offsite Oose Calculation Manual," Revision 1[8], and Regulatory Guide 1.109, Revision 1.I93 As specified in NUREG-0473, the QDCM is to be developed by the Licensee to document the methodology and approaches used to calculate offsite doses and maintain the operability of the radioactive effluent systems. As a minimum, the ODCM should provide equations and methodology for the following:
Alarm and trip setpoints on effluent instrumentation.
Liquid effluent concentrations in unrestricted areas.
Gaseous effluent dose rates at or beyond the site boundary.
Liquid and gaseous effluent dose contributions.
Liquid and gaseous effluent dose projections.
In addition, the ODCM should contain flow diagrams that define the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems. These flow diagrams should be consistent with the systems being used at the plant. A description and the location of samples in support of the environmental monitoring program are also needed in the ODCM.
2
3.
EVALUATION The Vermont Yankee Nuclear Power Station (VYNP) is a single unit BWR site. The ODCH provides formal and approved methods for the calculation of offsite concentrations, offsite doses and effluent monitor setpoints in order to comply with the Vcrmont Yankee technical specifications.
Liouid Effluent Pathways VYNP is located in southeastern Vermont. The site is situated on the west bank of the Connecticut River, 3.6 miles SSE of the town of North Hinsdale, New Hampshire, and 11.3 miles NNW of the town f Northfield, Massachusetts. The Connecticut River supplies makeup wacer to the once-through circulating water system, service water to the condenser, and also supplies dilution water at the discharge structure for the liquid radwaste discharge.
The liya:d radwaste system collects, processes, stores and disposes of all radioactive liquid wastes. A block diagram describing the liquid waste management system and effluent pathways is found in Figure 1 of this report which is a simplification of Figure 6-1 of the ODCM. The liquid radwastes are classified and treated as either high purity, low purity, chemical or detergent wastes.
Once the wastes are collected in the waste tanks shown in Figure 1, they are processed by the liquid radwaste treatment system and are either discharged or reused.
From the text in the ODCM it is inferred that simultaneous releases are not permitted but are batch discharged from one of the following tanks:
Detergent Waste Tank Floor Drain Sample Tank Waste Sample Tanks (2) 3 1
wa Detergent Filter 4
Waste Tank Floor Floor Drain
->; c Filter Drain Collector Demineralized Sample Chemical
>- Tank Tank Waste Tank V
Low Plant Puri ty Reuse Wastes Waste Collector
>- Tank
->3'- Fil ter-Waste Condensate High Puri ty Dentineralizer Sample Storage e
Wastes Tanks (2)
Tank Waste Surge i
Tank MI Dilution' Water J
Water Discharge Intake Circulation Water q
Structure
>1 Service Water 1
M M
Figure 1 Liquid Effluent Streams, Radiation Monitors, and Mcdwaste Treatment System at Vermont Yankee 4
i According to Section 6.1 of the ODCM, all liquid radwaste effluent meant for release, passes through the monitored liquid effluent discharge line. The radwaste effluents are then diluted with the circulating water discharge before release to the Connecticut River.
i In addi_ tion to the discharges through the above liquid effluent discharge line there are two liquid pathwayr ch:t are normally.
non-radioactive but have a finite possibility of having radioactive material injected into them. These liquid streams are the:
Servica Water Pathway Circulating Water Pathway Radiation monitoring systems detect any increase above the normal background concentration. The monitor for the circulating water pathway is a process monitor and is not identified in the technical specifications but is briefly discussed in the ODCM.
~
Radi~ activity released from the liquid radwaste system is the primary o
concern when assuring compliance to the concentration and the dose limit in the technical specifications.
Liouid Effluent Monitor Setcoints Sections 5.1.1 and 5.1.2 of the ODCM contain the methodologies used to determine the setpoint for the liquid radwaste and service water monitors in compliance with Note 5 of Table 3.9-1 of the VYNP technical specifications.
Section 5.1.1.1 contains the methodology for determining the alarm / trip setpoint for the liquid radwaste discharge monitor. The methodology is in agreement with the guidelines of NUREG-0133. However, due to the high level of the setpoint, it is recommended that an intermediate setpoint be included to provide alarm at 5
,. )
e a concentration slightly above the concentration planned for discharge with allowance to prevent spurious alarms.
This additional setpoint would guard against inadvertently releasing an incorrect tank.
In Section 5.1.2, it states that the alarm /setpoint for the service water monitor is set at three times the background of the instrument.
There is no automatic termination of release for the monitor.
In Section 2.2.3, it states that the alarm /setpoint for the circulating water monitor is set at three times the background of the instrument. There is no automatic termination of release for the monitor.
The methods to determine the setpoints for the liquid effluent radiation monitors are in agreement with the guidelines of NUREG-0133 and are censidered acceptable.
Gaseous Effluent Pathways The 94-meter plant stack is the only environmental release point for radioactive gaseous effluents at VYNp. The gaseous radwaste treatment system includes subsystems -that dispose of gases from the main condenser air ejectors, the startup vacuum. pump, the gland seal condenser, the standby gas treatment system, and the station ventilation exhausts.
According to Section 6.2, "the processed gases are routed to the plant stack for dilution and elevated release to the atmosphere."
The technical specifications identify noble gas monitors, an iodine and particulate samplers, and an effluent ficw measuring device to monitor gaseous effluent releases.
The stack effluents are continuously surveyed during release of noble gases. The iodine and particulate samplers are routinely analyzed in accordance with Technical Specification Table 4.8.2.
Figure 6-2 of the ODCM contains a diagram of the gaseous effluent treatment system which has been simplified in Figure 2 in this report.
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STACK Iodine Sampler Particulate Sampler M
' Noble Gas Monitor muLn Building Ventilation Standby Gas Treate.ent Gaseous Turbine Gland Seal /
Effluent Mechanical Vacuum Pumps From Air Ejectors 4
Delay Pipe A0G Bypass a
M A0G Bypass M
u
~ Hydrogen Dilution and Delay Moisture Removal Charcoal Moisture Recombiner ->
Tube
->- Dryer Subsystem -> Adsorber >- Filter >- Separator Subsystem Beds Startup Bypass I
i Figure 2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Vermont Yankee.
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4 Gaseous Effluent Monitor Setooints Table 3.9.2 of the technical specifications identify noble gas monitors for the steam jet air ejector (SJAE), the augmented off-gas system (A0G), and the plant stack. The monitor for the plant stack release has no automatic control functions but annunciated in the main control room; however, the A0G monitor located between the charcoal bed system and plant stack provides alarm and automatic termination of release.
Section 5.2.1 of the ODCM contains the methodology used to determine the setpoints for the plant stack and A0G noble gas monitors as required by Note 7 of Table 3.9.2 of the VYNP technical specifications.
Methodology for calculating the setpoints based on the skin and whole body dose rates are included with the more conservative setpoint being used.
In Section 5.2.1.1, the units given in the definition for DF ' are c
not consistent with the units in the definition given in Table 1.1-8.
The units in the definition are incorrect.
Section 5.2.2 of the ODCM, contains the methodology for determining the setpoint for the SJAE as required by Note 7 of Table 3.9.2 of the technical specifications. Technical Specification 3.8.K.1 limits the radioactivity release rate to less than or equal to 0:16 Ci/sec (after a 30-minute decay).
In Section 5.2.2.1 of the ODCM, it is stated that the SJAE noble gas monitor response is in counts per minute. The units should be mR/hr to be consistent with S, the detector efficiency, which has units of g
(mR/hr)/(gCi/cc).
With the exception of the minor discrepancies in the units, the methods for determining the setpoints for the noble gas monitors are in agreement with the guidelines of NUREG-0133 and are considered acceptable.
8
i Concentrations in liouid Effluents Section 2.0 of the ODCM contains the methodology, for calculating the radionuclides concentrations in the released liquid effluents, as required by Surveillance Technical Specification 4.8.A.I.
In Section 2.1, it is not clear how the concentration C,3 is determined. As inferred in p
Section 2.2.1, the parameter is determined by diluting the concentration determined from analysis of a proportional grab sample with the predicted flow at the point-'of discharge.
It is not clear what is meant by the
" predicted flow at the point of discharge", i.e., is it the dilution water flow or the sum of the dilution water. flow plus the circulating water flow plus.the service water flow? An equation should be included with the dilution flows identified. Also, in Section 2.2.1, a " representative grab sample" should be obtained for analysis instead of a " proportional grab sample."
Except for the lack of clarity for determining the diluted concentration, the methodology for determining radionuclides concentrations in the released liquid effluents is, in general, within the guidelines of NUREG-0133 and is considered acceptable.
Dose Rates in Gaseous Effluents Sections 3.4 and 3.5 contain the methods for determining the noble gas dose rates to the total body and the skin as required by Surveillance Technical Specification 4.8.E.1.
Compliance to the dose rate limits is continuously demonstrated when effluent release rates are below the plant stack noble gas monitor alarm setpoint. Demonstration of compliance to the dose rates are performed when the alarm setpoint is exceeded. There are two independent methods for determining the dose rates. Method I follows the NUREG-0133 methodology to predict the dose rate to the maximum exposed individual whereas Method II calculates the dose rate to a real individual and is only used if the results from Method I exceed the dose rate limits.
9
Method I On page 3-16 in Section 3.4.1, the total body gamma dose factor, DFBj for Xe-133 (referenced from Table-1.1-10) should have units 3
3 mrem-m /pCi-yr % stead of mrem-m /Ci-yr.
On page 3-21 in Section 3.5.1, the combined skin dose factor DF'j for Xe-133 (referenced from Table 1.1-10) should have units of mrem-sec/pCi-yr instead of mrem-sec/yCi-yr.
In Section 3.5.2 of the ODCM, the units for the constant 1.1 mrem / mrad are omitted in Equations 3-8 and 3-12.
Also, in Equation 3-13, the units T
3 3
for DF j should be mrad-m /pci-yr instead of mrem-m /%i-yr.
Method II
)
Throughnut the ODCM, Method II is described as an alternate calculation in the event the results from Method I exceed the limits.
Since Method II is intended to calculate the dose or dose rate to the real individual instead of the maximum exposed individual, then the methodolog t need not be contained in the ODCM. Nevertheless, if the Method I calculation exceeds the dose or dMe rate limit then Method II is applied.
It is stated in the ODCM that Method II uses the models, input data, ar.' assumptions of Regulatory Guide 1.109, Revision 1.
It is not clear what "YNSD" refers to in the descriptions for Method II.
1 Section 3.6 of the ODCM contains the methods for determining the dose rate to any organ due to the release of I-131, I-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days to areas at or beyorid the unrestricted area as required by Surveillance Technical Specification 4.8.E.2. Ir, the first paragraph of Section 3.6, i
1-132 is refe red to instead of I-133.
l 10 1
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The methodology of Method I for the dose rate due to the release of radioactive gases is, in general, in agreement with the guidelines of NUREG-0133 and is considered acceptable.
Dose Due to Liouid Effluents Sections 3.2 and 3.3 of the ODCM contain the methodology for determining the dose or dose commitment to the total body and any organ for a Member of the Public due to radioactive material released in liquid effluents as required by Surveillance Technical Specification 4.8.B.1.
The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and total body of the maximum exposed individual whose exposure pathways include consumption of fish, vegetation, meat, and, milk and the ground plane.
In Sections 3.2.1 and 3.2.2. equations defining DFlitb are omitted and should be included.
In Section 3.2.2, the dilution description on the bottom of page 3-7 appears to be incorrect since the dilution includes the river flow which is not permitted for a dose calculation. The allowed dilution is limited to on-site water. From Figure 6-1 in the ODCM, it appears that the on-site dilution cocid be a combination of the dilution l
water, circulating water, and the service water.
Nevertheless, the dilution for the dose calculation is the flow of all j
on-site water used for dilution averaged over the reporting period, e.g.,
the average flow during a calendar quarter.
In Equations 3-1 and 3-2, supporting equations describing the dose factor, DFlitb, are omitted and should be included. Without the equations and the site specific parameters, the reviewer was not able to reproduce the dose factor values in Table 1.1-11.
l 1
l l
11 l
The methodology for calculating the' dose due to the release of radioactivity in liquid effluents is, in general, in agreement with the guidelines of NUREG-0133. However, because of the method for calculating the dilution and the uncertainty in the data table, it is uncertain if the
. method is acceptable for the-dose calculation.
Dose Due to Gaseous Effluents Sections 3.7 and 3.8 of the ODCM contain the methodology for calculating.the cumulative gamma and beta air doses due to the release of radioactive noble gases as required by Surveillance Technical Specification 4.8.F.1.
The methods for calculating the air dose due to the release of radioactive noble gase: are in agreement with the guidelines of NUREG-0133 and are considered acceptable.
Section 3.9 of the ODCM contains the methodology for calculating the cumulative dose due to the release of I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than eight days as required by Surveillance Technical Specification.4.8.G.I.
In Section 3.9.1 there are no equations for the dose factors, DFGico. The equations and site specific parameters should be included to show the basis for the factors. Table 1.1-12 contains site specific dose factors for the critical organ, and critical age group individual exposed to all pathways living at the maximum offsite atmospheric dispersion factor location. However, without the equations and the site specific parameters the reviewer was unable to reproduce the values in the table.
The methodology for calculating the cumulative dose due to the release of I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than eight days is, in general, in agreement with the guidelines of Regulatory Guide 1.109, Revision 1 end NUREG-0133. However, I?
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because the dose factors in Table 1.1-12 cannot be reproduced, it is uncertain if the dose calculations will result-in values that can be used to compare with the~ dose limits of Technical Specification 3.8.G.I.
Dose Pro.iections Section 3.2 of.the ODCM describes the method used.to project doses due to the expected release of radioactive liquids to determine'when the liquid radwaste treatment system shall be operated as required in Surveillance. Technical Specification 4.8.C.I.
The methodology for determining the dose projection due to liquid radwaste effluents is in agreement with NUREG-0133 and is considered acceptable.
Technical Specification 4.3.I.1 does not require that dose projection methods be included in the 00C11 to determine required use of the Ventilation Exhaust Treatment System. Technical Specification 4.8.I.1 requires that monthly dose calculations be made in accordance with methods in the'0DCM described in a previous section of this report.
It is not clear how the monthly dose calculation based on actual releases can be used for the dose estimate required by Technical Specification 3.8.I.1.
Diaarams of Effluent. Pathways Diagrams for the radioactive liquid and gaseous treatment systems and release pathways are shown in Figures 6-1 and 6-2 of the 00CM but are illegible and should be replaced. A simplifiiB flow diagram of the solid radwaste treatment system is missing from the ODCM and should be included.
Total Dose Section 3.12 of the ODCM contains the methodology for calculating the total dose contributions including direct radiation as required by Technical Specifications 4.8.M.2.
The methods for the total dose are in agreement'with the guidelines of NUREG-0133 and are considered acceptable.
13
Environmental Monitorino Proaram Section'4.0 of the ODCM contains specific parameters of distance arid the direction sector from the site and additional information for each and every sample identified'in Environmental Monitoring Table 3.9.3 for VYNP.
In Section 3.10.3, the ODCM states that measured meteorological data during the five year period 1981 through 1985 were analyzed to determine the values and locations of maximum offsite annual average atmospheric dispersion factors. These factors are used in Method I calculations.
In Section 4.2, the total "in-valley" wind flow time should be 67 percent instead of 76 percent. The environmental program is, in general, in compliance with Technical Specification Table 3.9.3.
Summary In summary, the Licensee's ODCM uses documented and approved methods that are, in general, consistent with the methodology and guidance in NUREG-0133 and Regulatory Guide 1.109, Revision 1.
However, it is recommended that the NRC request another revision to address the discrepancies.
14
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4 '. CONCLUSIONS L
'The Licensee's ODCM, updated through Revision 4, dated December 30, 1987 for VYNP was reviewed.
It was determined that the ODCM uses methods that are, in general, consistent with the guidelicas of NUREG-0133. The methodology in most sections of the 00CM~are acceptable for use in dem. o.urating compliance to the ' radiological effluent technical spet.r1 cations. However, it is recommended that another revision to the ODCM be submittsd to address the discrepancies identified in the review.
In Section 2.1, it is not clear how the concentration C,j p
is determined. An equation should be included in Section 2.1 to show how the concentration is determined and to identify the dilution.
In Section 2.2.1 it is not clear what is meant by the
" predicted flow at the point of discharge."
In Section 2.2.1, a " representative grab sample" should be obtained ter analysis instead of a " proportional grab sample."
In Section 3.2.1 and 3.2.2, equations defining DFlitb are omitted and should be included.
In Section 3.2.2, the dilution description on the bottom of page 3-7 appears to be incorrect's'ince the dilution includes the river flow which is not permitted for a dose calculation. The allowed dilution is limited to on-site water. From Figure 6-1 in the ODCM, it appears that the ca-site dilution could be a combination of the Dilution Water, Circulating Water, and the Service Water.
l In Section 3.2.2 the dilution for the dose calculation is the flow of all on-site water used for dilution averaged over the reporting period, e.g., the average flow during a calendar quarter.
15
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_.________.___...m___
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In Equations 3-1 and 3-2,1 supporting equations describing the 1
f
' dose factor, DFlitb, are omitted and should be. included.
1 In Table 1.1-11, the reviewer was unable to r!):roduce the dose factor values.
In Table 1.1-12, the reviewer was unable to reproduce the
-dose factor values.
In.Section 3.6, a typo exists in the first paragraph where I-133 is identified as I-132.
In Section 3.4.1, page 3-16 of the ODCM the total body dose I
factor, DFBj for Xe-133 referenced from Table 1.1-10 should l
3 3
have units of mrem-m /pCi-yr instead of mrem-m /Ci-yr.
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In Section 3.5.1, the combined skin dose factor l
DF'j for Xe-133 referenced from Table 1.1-10 should have units of mrem-sec/pCi-yr instead of mrem-s'ec/yCi-yr.
In Section 3.5.2, the units for the constant 1.1 mrem / mrad
{
are omitted in Equations 3-8 and 3-12.
Also, in Equation 3-13, 3
the units for DF7j should'be mrad-m /pCi-yr instead of 3
mrem-m /pCi-yr.
In Section 3.9.1, supporting equations used to calculated the j
dose factor DFGjeg are omitted and should be included.
^
In Section 4.2 of the ODCM, the total "in-valley" wind flow time should be 67 percent instead of 76 percent.
In Section 5.2.1.1 of the ODCM, the units given in the definition of DF ' are not consistent with the units for the c
definition given in Table 1.1-8.
16 t
In Section 5.2.2.1, the units for the SJAE noble gas monitor response should be mR/hr to be consistent with S, the detector g
efficiency which has units of (mR/hr)/(pci/cc),
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~~
Diagrams for the radioactive liquid and gaseous treatment systems and release pathways are shown in Figures 6-1 and 6-2 of the ODCM but are illegible and should be replaced. A simplified flow diagram of the solid radwaste treatment j
system is also missina from the ODCM.
The following are not discrepancies of the ODCM, but are suggestions or areas of confusion that should be addressed by the Licensee:
An intermediate or low level setpoint should be included with the liquid radwaste monitor.
It is not clear what "YNSD" stands for when performing a Method II calculation.
It is not clear how the monthly dose calculation based on actual releases required by Technical Specification 4.8.I.1 can be used for the dose estimate required by Technical Specification 3.8.I.1 to determine when to use the Ventilation Exhaust Treatment System.
17
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5.
REFERENCES
- 1.. Title 10, Code of Federal Regulations, Part 50, Appendix. I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion, ' As Low As Is Reasonably Achievable,' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor
~
Effluents. "
l 2.
Letter from V. L. Rooney (NRC) to R. W. Capstick (VYNPC),
Subject:
Approval of the Offsite Dose Calculation Manual, October 9,1984.
3.
i.etter from J. B. Sinclair (VYNPC) to D. B. Vassallo (NRC),
Subject:
Vermont Yankee Off-Site Dose Calculation Manual (0DCM), March 5,1984.
4.
Letter from R. W. Capstick (VYNPC) to R. Vollmer (NRC),
Subject:
Vermont Yankee Semiannual Effluent Release Report, March 1,1987.
5.
Letter from R. W. Capstick (VYNPC) to NRC,
Subject:
Vermont Yankee Semiannual Effluent Release Report, February-29,1988.
6.
" Radiological Effluent Technical Specifications for Boiling Water Reactors," Rev. 3, Draft 7, intended for contractor guidance in reviewing RETS proposals for operating reactors, NUREG-0473, September 1982.
7.
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, A Guidance Manual for Users of Standard Technical Specifications," NUREG-0133, October 1978.
8.
" General Contents of the Offsite Dose Calculation Manual," Revision 1, Branch Technical Position, Radiological Assessment Branch, NRC, February 8, 1979.
9.
" Calculation of Annual Doses of Evaluating Compliance with 10 CFR,50, Appendix I," Regulatory Guide 1.109, Rev.1, October 1977.
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YE6ni'O'f" Evaluation Report for the Evaluation of
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ODCM Through Revision 4 Vermont Yankee Nuclear j
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May 1988 T. S. Bohn, C. R. Amaro,
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Radiological Physics EG&G Idaho, Inc.
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P. O. Box 1625 Idaho' Falls, ID 23415 D6034
.....o...............,,.....u..,.c, Office of Nuclear Reactor Regulation Final U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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The Offsite Dose Calculation Manual for the Vermont Yankee Nuclear Power Station (VYNP) contains current methodology and parameters used in the calculation of offsite doses due to radioactive liquid and gaseous effluents, in the calculation of gaseous and liquid effluent. monitoring alarm / trip setpoints, j.
and in the execution of the environmental radiological monitoring program.
Revision 0, dated March 5, 1984 was submitted to the NRC and subsequent Revisions 1, 2, and 3 were reported to the NRC in the Semiannual Effluent Report for July-December 1986. The latest revision, Revision 4, was reported to the NRC in the Semiannual Effluent Report for July-December 1987. The NRC transmitted Revision 0'along with Revisions 1, through 4 to the Idaho National Engineering Laboratory (INEL) for review. The ODCM updated through Revision 4 was reviewed in its entirety by'EG&G Idaho at the INEL and the results of the review are presented in this report.
It was determined that the ODCM updated through Revision 4 uses methods that are, in general, in agreement with the guidelines of NUREG-0133. However, it is recommended that another revision to the ODCM be l
submitted to address the discrepancies identified in the review.
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