ML20236V308
| ML20236V308 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/28/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236V249 | List: |
| References | |
| NUDOCS 8712040225 | |
| Download: ML20236V308 (26) | |
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h UNITED STATES y
p, NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
%...../
SAFETY EVALUATION BY THE' 0FFICE OF NUCLEAR REACTOR REGULATION RELATING TO ACCEPTANCE OF THE OFFSITE DOSE CALCULATION MANUAL UPDATED THROUGH REVISION 1 BOSTON EDIS0N PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-?93
1.0 INTRODUCTION
On August 30, 1985 the staff issued Amendment No. 89 to Facility Operating License No. OPR-35 for the Pilgrim Nuclear Power Station (Pilgrim). The amendment incorporated the Radiological Effluent Technical Specifications (RETS) into the Pilgrim Technical Specifications-(TS). Section 6.9.C.3 of the TS referenced an Offsite Dose Calculation Manual (ODCM) and pretcribed the methods for reporting changes.
l 2.0 EVALUATION The docketed submittal on June 16, 1983, of an ODCM by Boston Edison (licensee) received NRC approval by letter dated August 30, 1985 from P. H. Leech to the licensee. Recently in their Semi-Annual Radioactive Effluent and Waste Disposal Report for the Period January 1 through June 30, 1987, submitted by [[letter::BECO-87-141, Application for Amend to License DPR-35 Revising 870601 Application to Change Tech Specs 3.5.C.1 & 3.5.D.1 to Specify,Quantitatively,Reactor Operating Conditions for Which HPCI & RCIC Required to Be Operable|letter dated September 1,1987]], the licensee submitted revised pages to the ODCM, labeled Rev.1. As part of an ongoing review of licensee ODCMs, the Pilgrim ODCM updated through Revi-sion 1, has been reviewed for us in its entirety by EG&G Idaho, Inc.
8712040225 871028 "
PDR ADOCK 05000293 P
I The contrac-(EG&G) as part of our technical assistance contract prooram.
tor's Technical Evaluation Report (TER), which is enclosed as Appendix 0, EGG-PHY-7725, provides a technical evaluation of the compliance o' the licensee's submittal with NRC criteria. The staff has reviewed this report and agrees with the evaluation that the Pilgrim OnCM, Lpdated through Revision 1, uses documented and approved methods that are general-ly consistent with the methodology and guidelines in NUREG-0133. There--
fore, we conclude that this ODCM is an acceptable interim reference for use with the Pilgrim Technical Specifications. However, the enclosed TER j
lists a number of discrepancies and suggestions that should be addressed within six months in a new revision to the Pilgrim ODCM.
3.0 CONCLUSION
S The Pilgrim ODCM, updated through Revision 1, is acceptable on an interim basis. Discrepancies noted in the attached TER should be addressed within 4
six months in a revised ODCM submission.
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l APPENDIX D Evaluation of Changes to the ODCM, PCP, and Radwaste Treatment Systems (Pilgrim Nuclear Power Station)
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D.1 EVALUATION OF CHANGES TO THE ODCM I
The Boston Edison Company (BEco) prepared an Offsite Dose Calculat' ion l
Manual (ODCM) for the Pilgrim Nuclear Power Station. The Boston Edison l
Company submitted this ODCM, Revision 0, dated 6/10/83 to the Nuclear Regulatory Conrnission (NRC) with letter dated June 16,1983.[13 The NRC found it to be generally consistent with NRC criteria and an acceptable referen a as stated in the NRC letter and SER dated August 30,1985.[2]
The licensee submitted changes labeled Rev.1 to the Revision 0 ODCM in the Semiannual Radiological Effluent Release Report issued for the first 6 I
months of 1987.[33 These changes have been incorporated into the
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Licensee's existing ODCM and, at the request of the NRC, the entire ODCM l
i reviewed as a whole. The result of the evaluation is intended to be a stand-alone document, and is given in Supplement I to Appendix D.
0.2 EVALUATION OF CHANGES TO THE PCP No technical specification exists requiring use of a Process Control Program (PCP). Consequently, it appears that the licensee has not j
prepared a PCP.
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D.3 REPORTED CHANGES TO THE RADWASTE TREATMENT SYSTEMS l
j No technical specification exists requiring the licensee to report to i
the NRC major changes made to the liquid, gaseous, or solid radwaste j
l treatment systems. Therefore, if changes are made to these systems, they are reported to the NRC in the annual FSAR updates.
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1 D.4 REFERENCES 1.
Letter from W. D. Harrington (BEco) to D. B. Vassallo (NRC),
Subject:
Offsite Dose Calculation Manual, June 16, 1983.
2.
Letter from P. H. Leech (NRC) to W. D. Harrington (BEco),
Subject:
j Acceptance of Dffsite Dose Calculation Manual (ODCM) for Pilgrim Nuclear Power Station Unit 1, August-30, 1985.
3.
Letter from R. G. Bird (BEco) to Document Control Desk (NRC),
Subject:
Semi-Annual Radioactive Effluent and Waste Disposal Report for the l
Period January 1 throughl June 30, 1987, September 1, 1987.
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l SUPPLEMENT 1 to APPENDIX D EVALUATION OF CHANGES TO THE ODCM I
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1.
INTRODUCTION purpose of Review This document reports the review and evaluation of the latest revised version of the Offsite Dose Calculation Manual (ODCM) submitted by the Boston Edison Company (BEco), the licensee for the Pilgrim Nuclear Power Station. The ODCM is a supplementary document for implementing the Radiological Effluent Technical Specifications (RETS) in compliance with 10 CFR 50, Appendix I requirements.E13 plant-Specific Background The Boston Edison Company submitted ODCM, Revision 0, dated 6/10/83 for the Pilgrim Nuclear Power Station to the Nuclear Regulatory Commission l
(NRC) with letter dated June 16,1983.[2] The NRC found it to be generally consistent with NRC criteria and an acceptable reference as stated in the NRC letter and SER dated August 30,1985.[33 The licensee submitted changes labeled Rev.1 to the Revision 0 ODCM with the Semiannual Radiological Effluent Release Report issued for the first 6 months of 1987.[93 These changes have been incorporated into the Licensee's existing ODCM and, at the request of the NRC, the entire ODCM reviewed as a whole. The result of the evaluation is intended to be a stand-alone document and is presented in this report.
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2.
REVIEW CRITERIA Review criteria for the ODCM were provided by the NRC in three documents:
NUREG-0472, RETS for PWRs[43 NUREG-0473, RETS for BWRs[5]
NUREG-0133, Preparation of RETS for Nuclear Power Plants.[6]
The following NRC guidelines were also used in the ODCM review:
" General Contents of the Offsite Dose Calculation Manual," Revision 1[73, and Regulatory Guide 1.109.[8]
As specified in NUREG-0472 and NUREG-0473, the ODCM 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:
o Alarm and trip setpoints on effluent instrumentation o
Liquid effluent concentrations in unrestricted areas o
Gaseous effluent dose rates at or beyond the site boundary o
Liquid and gaseous effluent dose contributions o
Liquid and gaseous effluent dose projections.
J In addition, the ODCM should contain flow diagrams, consistent with the systems being used at the station, defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems. A description and the location of samples in support of the environmental monitoring program are also needed in the ODCM.
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3.
EVALUATION The Pilgrim Nuclear Power Station is a single unit nuclear site.
As stated in the introduction of the ODCM, the manual contains information and methodologies to be used by the Pilgrim Nuclear Power Station. The manual is structured such that it should be unnecessary to refer to other documents to perform the indicated calculations.
Liquid Effluent pathways l
The Pilgrim Nuclear power Station is located on the western shore of
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Cape Cod Bay in the town of Plymouth, Plymouth County, Massachusetts.
Liquid effluents are discharged with the once-through condenser cooling water into the Say. The principal sources of liquid radwaste are the following:
Clean Waste Tanks Chemical Waste Tanks Miscellaneous Waste Drain Tanks 1
i Radwaste, Released Directly to Environment i
1 Effluents from the first three sources are processed in the liquid effluent treatment system (LETS). The fourth source is mentioned in a later paragraph. The LETS was designed to handle radioactive, chemical and miscellaneous liquid wastes. There is one environmental release point at the site for the processed liquid radwastes. The system is operated as a batch system and the operating procedures used for all liquid radwaste equipment are based on batch processing throughout the system. This type-of operation allows time to sample and check the effluent batches before-and after each process step to prevent inadvertent discharge of waste having a radioactivity level above the control limit.
Each batch is analyzed prior to release for gross beta / gamma activity, and the resulting specific activity is used to determine the discharge flow rate.
Liquids with radioactivity levels exceeding specified limits are recycled for further processing.
From the description in ODCM Section 3.2.3, it appears l
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u that discharges from the first three sources are released-to a common header where they are monitored for radiation. The radiation monitor provides alarm and automatic termination of release through the discharge-valves upon a high radiation condition. There are two waste discharge
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valves: one is located on a one-inch line from the common header and the other is on a two-inch line from the common header. The batch release is l
briefly discussed in ODCM Section 3.1.3.
During liquid releases, the flow rates, and activity levels are continuously recorded. According to 0DCM Section 3.3.2, the radwaste discharge flow is maintained at a predetermined level (not to exceed 200 gpm). The liquid radwaste effluents are released to the condenser cooling water discharge canal prior to discharge into Cape Cod bay.
Therefore, the flow control valves and the radiation monitors are the primary methods for controlling discharges from the liquid radwaste system.
In addition to batch releases from the LETS, batch releases from other sources directly to the environment are permitted provided that at least two independent samples are analyzed in accordance with Specification 4.8.A.1 as described in ODCM Section 3.1.3.
In addition, independent verifications of the release rate calculations and discharge valving must be performed. Concentrations released to the unrestricted areas must also be limited to the values specified in 10 CFR 20. The
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location of this environmental release point should be identified in the 4
ODCM.
Licuid Effluent Monitor Setooints ODCM Section 6.1 contains the methodology for determining the setpoint j
for the liquid radwaste radiation monitor.
The monitor provides alarm and automatic termination of release. The setpoint ensures that the concentration of liquid effluents discharged does not increase above the value for which the maximum permissible discharge flow was established.
In other words, the setpoint is set at the level determined from the i
prerelease grab sample.
Since there is no margin allowed, the monitor should be alarming continuously during a release thus l
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preventing the release.
If the setpoint is increased to allow for a margin, then the discharge flow (Section 3.3.2) must be decreased accordingly.
In ODCM Section 6.1.3, the documentation for estimating the monitor's efficiency " based on prior release experience" is not referenced'. The methodology described in ODCM Section 6.1 for determining the setpoint for the radiation monitor in the liquid radwaste system is, in general, in agreement with the guidelines of NUREG-0133 to provide reasonable assurance that the concentration limits of Technical Specification 3.8.A.1 will not be exceeded. However, it is not clear if the monitor's actual setpoint is set at the level described in this section.
Gaseous Effluent Pathways l
There are two monitored environmental gaseous effluent release points at the Pilgrim Nuclear Power Station:
Main Stack Gas Release Reactor Building Exhaust Vent Release The technical specifications identify noble gas monitors and iodine and particulate samplers.
Each release point is continuout,j surveyed during releases for noble gases by two monitors.
Each monitor has two upscale trips and one downscale trip. Each trip initiates an alarm in the main control room, but no automatic termination is provided. The upscale alarms indicate high radiation and the downscale alarm indicates instrument trouble.
Each release point has iodine and particulate samplers in the gas monitoring stream The samplers are routinely analyzed in accordance with Technical Specification Table 4.8-3.
All gaseous effluent releases from the reactor building exhaust vent are treated as ground level releases and the main stack releases are treated as elevated releases.
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Gaseous Effluent Monitor Setpoints Section 6.2 of the ODCM contains the methodology used to determine the setpoints for the noble gas radiation monitors.
In items 3) ard 4) however, re'ference is made to the equation of Section 4.0 but instead should be made to the equations in Sections 4.F and 4.G.
Simultaneous releases from these two release points are considered when determining each monitor's setpoint. This section is, in general, in agreement with the guidelines of NUREG-0133 to provide reasonable assurance that the noble gas dose rate limits of Technical Specification 3.8.D.'1 will not be exceeded.
1 Concentrations.in Liouid Effluents l
Section 4.A of the ODCM contains the methodology for demonstrating l
I that the radionuclides concentrations in the released liquid effluents are in compliance with the technical specification.
The option for determining the quantity C j in the concentration equation by " estimates w
based on prior experience" is not acceptable as this is not permitted in the liquid sampling Table 4.8-1 of the Technical Specifications.
The methodology however, is in general, within the guidelines of NUREG-0133 and should provide reasonable assurance that the concentrations at the point of release are maintained within the limits of Technical Specification 3.8.A.1.
3ose Rates in Gaseous Effluents The equations in Sections 4.0 through 4.L are general equations that are used to determine both the doses and the dose rates due to the gaseous effluents.
It is not clear from the equations if contributions from both the main stack and the reactor building vent are included.
Each individual equation should contain a summation over the stack and vent contributions.
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l Sections 4.F through Section 4.G contain the equations for calculating noble gas dose rates to determine compliance with dose rate Technical Specification 3.8.D.1.a.
The dose rates due to the release of noble gases are assured to be within the dose rate limits by correctly setting the setpoints'for the noble gas monitors as previously described in this report.
Sections 4.H through 4.L of the ODCM contain the equations for determining dose rates for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days to areas at and beyond the site boundary as specified in Technical Specification 3.8.D.1.b.
The titles however identify " Halogens, Particulate and others" instead of " iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days". The bases statement for Technical Specification 3.8.D states that the release rate of these nuclides restricts at all times the thyroid dose rate to a infant via the cow-milk-infant pathway to less than or equal to 1500 mrems/ year. The more restrictive age group however is the child instead of the infant as identified in Revision 3 Draft 7" of NUREG-0473 dated September 1982.[5] The: licensee should consider changing the bases statement in their next request for a technical specification revision.
G The equation for C j in Section 4.H contains an "i".in the 7
denominator whereas it should be "Aj".
The constants 1.2x10,
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2.2x10, 5.5x10, and 1.1x108 in Sections 4.J through Section 4.L are not defined.
The definition for the quantity Qi should not include l
the word " annual" since it is already being considered "for the period".
The time unit " hours" has been omitted from the definition for t.
In e
general, the sections dealing with " Doses for Gaseous Effluents" could include supplementary information to provide guidance and clarity to the user.
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It is uncertain if the maximum organ dose is identified since the j
technical specification bases statement identifies the infant age group instead of the child age group.
Nevertheless, the equations in Sections 4JH through 4.L are in agreement with NUREG-0133 and Regulatory Guide 1.109 and should provide reasonable assurance that the dose rate limit of Technical Specification 3.8.D.1.b will not be exceeded.
Dose Due to Liouid Effluents Sections 4.B and 4.C of the ODCM contain the metnod for determining the dose to the maximum exposed member of the public due to radionuclides identified in liquid effluents to demonstrate compliance with the dose j
limits of Technical Specification 7.2.
The equations in Sections 4.B and 4.C are in agreement with those of Regulatory Guide 1.109. The methods include all age groups using the aquatic foods, and shorf 'ne deposits pathways.
The calculations could be made to only the at(, age group since NUREG-0133 identifies the adult as the limiting age group.
Condenser cooling is a once-through system and provides dilution water for the liquid radwaste releases.
The dilution flow in the equations represented by "F" and "M " should be replaced with the average p
condenser cooling flow for the period to change the dilution flow to the average flow of the discharge canal during the reporting period.
The methodology for calculating doses due to the release of j
radioactivity in liquid effluents is, in general, in agreement with the guidelines of NUREG-0133 and the methodology should provide reasonable assurance that the calculated doses will be within the limits of Technical Specification 3.8.A.1 Dose due to Gaseous Effluents Sections 4.0 and 4.E of the ODCM contain the equations for calculating the cumulative dose due to the release of radioactive noble gases in gaseous effluents to demonstrate compliance with the dose limits of 01-10
l Technical Specification 7.3.
The values for X/Q in Table 5-1 are evaluated at and beyond the site boundary. The table lists the X/Q values for both the main stack and the reactor building vent.
As mentioned previously, it is not clear from the equations if the dose contributions from both the main stack and the reactor building vent are included.
Each individual equation should contain a summation over the stack and vent contributions.
Except for this uncertainty concerning the dose contribution from both release points, the methodology for calculating.the maximum dose to air due to the release of radioactive noble gases is, in general, in agreement with the guidelines of NUREG-0133 to provide l
reasonable assurance that the dose limits of Technical Specification 7.3 will not be exceeded.
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Sections 4.H through 4L of the ODCM contain the equations for l
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 to demonstrate compliance with the dose limits of j
With the exception of the previously j
mentioned discrepancies which will be identified in the conclusion section, the methodology is, in general, within the guidelines of NUREG-0133 and should provide reasenable assurance that the dose limits of l
Technical Specification 7.5 will not be exceeded.
Dose Projections Technical Specification 3.8.C.1 requires that the liquid radwaste treatment system be operated whenever doses due to liquids to be released would exceed certain dose limits. However, the corresponding Surveillance Specification 4.8.C.1 requires that the doses be calculated due to liquids that have been released. Thus, the surveillance specification does not require the dose projection required by the technical specification.
The ODCM, consequently, does not include a dose projection due to liquid radwaste releases. A dose projection should be incorporated into the ODCM to satisfy the Technical Specification 3.8.C.1 requirements.
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There is no technical specification identifying required use of the i
ventilation exhaust treatment system.
Consequently, there is no requirement for projecting doses due to gaseous releases from the reactor building exhaust vent.
Diagrams of Effluent pathways Simplified diagrams of the liquid and gaseous radwaste treatment systems are contained in Figure 8-1 and Figure 8-2, respectively. A simplified diagram illustrating the solid waste treatment system is not included in the ODCM.
j Figure 8-1 should be modified to show the one-inch and the two-inch discharge lines, the release pathway to the discharge canal, and the environmental release point for liquid radwastes released without treatment.
Figure 4.8-2 in the technical specifications shows the drywell effluents being released to the main stack whereas Figure 8-2 in the ODCM shows these effluents being released to the reactor building vent. The figures should be consistent.
I Diagrams showing the radiation monitoring systems are shown in Figures 3.1, 3.2, and 3.3.
These radiation monitoring system diagrams are illegible and should be replaced.
1 Total Dose There is no separate section in the ODCM addressing the 40 CFR 190 total dose limits of Technical Specification 7.5.
Therefore, there is no expression given for calculating the total dose from the liquid, gaseous, and direct radiation contributions.
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Environmental Monitoring program Table 7-1 in Section 7.0 of the ODCM identifies specific parameters j
I for distan'ce and the direction sector from the site and additional information for each and every sample identified in Environmental Monitoring Table 8.1-1 of Technical Specification 7.0.
The direction for Duxbury appears to be NW of the plant site instead of "SSW-SW" as indicated in Table 7-3.
Figures 7.1 through 7.4 are illegible and should be replaced.
j Summary In summary, the licensee's ODCM uses documented and approved methods that are generally consistent with the methodology and guidance in NUREG-0133. However, because of the discrepancies identified in this review, it is recommended that the NRC request a revision to address the concerns identified in this review.
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CONCLUSIONS The licensee's ODCM, updated through Revision 1, for the Pilgrim Nuclear Power Station was reviewed.
It was determined that the ODCM uses methods that are, in general, consistent with the guidelines of NUREG-0133. However, it is recommended that a revision to the ODCM be i
submitted to address the discrepancies identified in the review.
The following is considered to be a major discrepancy:
o In Section 4.1, it is uncertain if the dose rate to the child's thyroid is identified as the maximum organ dose since the bases statement in Technical Specification 3.8.D identifies the infant age group instead of the child age group.
The following are additional discrepancies:
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In Section 3.1.3, the location of the environmental release point l
for liquid radwaste batch releases from sources other than the liquid radwaste treatment system should be identified in the ODCM.
o Figures 3.1, 3.2, and 3.3 contain diagrams showing the radiation monitoring systems. These radiation monitoring system diagrams are illegible and should be replaced.
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In Section 4.A, the option for determining the quantity Cwi in l
the concentration equation by " estimates based on prior i
experience" is not consistent with liquid sampling Table 4.8-1 of the technical specifications.
o In the equations of Sections 4.B and 4.C, the dilution flow is represented by "F" and "M " and should be replaced with the p
average condenser cooling flow for the period to change the dilution flow to the average flow of the discharge canal during the reporting period.
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o In Sections 4.D through 4.L. it is not clear from the equations that simultaneous dose rate contributions from the main stack and the reactor building vent are included.
l'n Sections 4.H through 4.L. the titles identify " Halogens, o
Particulate and others" instead of " iodine-131, iodine-133, tritium, and all radionuclides'in particulate form with half lives greater than 8 days".
G In Section 4.H. the equation for C j contains an "i" in the o
denominator whereas it should be "Aj".
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o In Sections 4.J through 4.L the constants 1.2x10, 2.2x10,
7 8 are not defined.
5.5x10, and 1.1x10 o
In Section 4.L. the definition for the quantity Qi should not include the word " annual" since the air dose or air dose rate is already being considered "for the period".
o In Section 4.L the time unit " hours" has been omitted from the definition for t.
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In Section 6.1, the setpoint for the liquid radwaste monitor is set to the level determined from the prerelease grab sample with no margin allowed.
It is not clear if plant operation is consistent with the ODCM description since the monitor should be alarming continuously during a release, thus preventing the release.
o In Section 6.1.3, the documentation for estimating the monitor's efficiency " based on prior release experience" is not referenced.
o In Section 6.2, items 3) and 4) reference the equation of Section 4.0 and should reference the equations in Sections 4.F and 4.G.
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o A calculation should be iaciuded in the ODCM to project doses due to the release of radioactivity in liquid effluents to satisfy-the requirement of Technical Specification 3.8.C.I.
o-A' simplified diagram illustrating the solid' waste treatment system is not included in the ODCM.
o There is no separate section in 'the ODCM addressing the total-dose limits of Technical Specification 7 5 with methodology for.
calculating the total dose from the liquid, gaseous, and diret.t radiation contributions.
I o
The direction for Duxbury is NW of the plant site instead of "SSW-SW" as indicated in Table 7-3.
o Figures 7.1 through 7.4 are illegible and should be replaced.
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Figure 8-1 should be modified to show the one-inch and the two-inch discharge lines, the release pathway to the' discharge canal, and the environmental release point for liquid radwastes released without treatment.
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o Figure 8-2 in the ODCM shows the drywell effluents.being released to the reactor building vent whereas Figure 4.8-2 in the technical specifications shows these effluents being released to the main stack. The figures should be correct and consistent.
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The following are not discrepancies in the ODCM, but are suggestions that should be brought to the attention of the licensee:
j o
Table 2.1 does not contain reference to Section 4.L.
o Section 4 in the Table of Contents only contains Sections 4.A through 4.K instead of through 4.L.
o In Sections 4.8 and 4.C, the calculations could be made to only the adult age group since NUREG-0133 identifies the adult as the-limiting age group.
o The licensee should consider modifying the bases statement in Technical Specification 3.8.D'to change from the infant to the child age group which is the most restrictive age group for the dose rate calculation.
o The licensee should modify Surveillance Specification 4.8.C.1 in the technical specifications to include a dose projection to satisfy the requirement of Technical Specification 3.8.C.1.
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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 I
Effluents."
i 2.
Letter from W. D. Harrington (BECo) to D. B. Vassallo (NRC),
Subject:
i Offsite Dose Calculation Manual, June 16, 1983.
3.
Letter from P. H. Leech (NRC) to W.,D. Harrington (BECo),
Subject:
Acceptance of Offsite Dose Calculation Manual (ODCM) for Pilgrim Nuclear Power Station Unit 1, August 30,.1985.
4.
" Radiological Effluent Technical Specifications for Pressurized Water Reactors," Rev. 3, Draft 7",
intended for contractor guidance in reviewing RETS proposals for operating reactors, NUREG-0472, September 1982.
l S.
" 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.
6.
" Preparation of Radiological Effluent Technical Specificatic,ns for Nuclear Power Plants, A Guidance Manual for Users of Standard i
Technical Specifications," NUREG-0133, October 1978.
7.
" General Contents of the Offsite Dose Calculation Manual," Revision 1 Branch Technical Position, Radiological Assessment Branch,-NRC -
February 8, 1979.
i 8.
" Calculation of Annual Doses to Man from Routine Releases of. Reactor
.i Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Regulatory Guide 1.109, Rev. 1, October 1977.
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9.
Letter from R. G. Bird (BEco)'to Document Control Desk (NRC),.
Subject:
- 1 Semi-Ar.nual Radioactive Effluent and Waste Disposal Report for the Period January 1 through June 30, 1987, September 1, 1987.
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