ML20057E224
| ML20057E224 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/29/1993 |
| From: | CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | |
| Shared Package | |
| ML20057E204 | List: |
| References | |
| NUDOCS 9310080144 | |
| Download: ML20057E224 (11) | |
Text
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i ATTACHMENT A PROPOSED TECHNICAL SPECIFICATION CHANGES l
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l CONSOLIDATED EDISON COMPA!W OF NIN YORK, INC.
INDIAN POINT UNIT NO. 1 DOCKET NO.50-003 SEPTEMBER, 1993 9310000144 930929 C
i PDR ADOCK 05000003 P7 P
PDR V
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l Radioactive Effluent Release Reoort i
6.8 Routine Radioactive Effluent Release Reports covering the previous 12 nonths of operation shall be submitted by May 1 of each year.
6.9 The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in the Regulatory Guide 1.21 " Measuring, Evaluating, and Reporting P.adioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, i
The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint freg stability.gency' distribution of wind speed, wind direction, and atmospheric This same report shall include an assessment of the radiation deses due to the radioactive liquid and gaseous effluents released from the i
unit or station during the previous calendar year.
This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the report period. All assumptions used in making these assessments, i.e.,
specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive naterials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.
Approximate and conservative approximate methods are acceptable.
The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).
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In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
Amendment No.
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4 ATTAC!ilENT B PROPOSED TECHNICAL SPECIFICATION CHANGES l
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CONSOLIDATED EDISON COMPAl# OF NEW YORK, INC.
INDIAN POINT UNIT No. 2 DOCKET NO. 50-247 SEPTEMBER, 1993 1
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The reports shall also include the followings a summary description of the radiological environmental monitoring program; at least two legible 4
maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactors the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 4.11.C; discussion and all deviations from the sampling schedule of Table 4.11-1; and discussi>n of all analyses in i
which the LLD required by Table 4.11-3 was not achievable.
RADIOACTIVE EFFLUENT REPORT 6.9.1.6 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted I
by May 1 of each year.
The Radioactive Effluent Release Report shall include a summary of the i
quantities of radioactive liquid and gaseous effluents and solid waste l
released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized en a quarterly basis following the format of Appendix B thereof.
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One map shall cover stations near the site boundary; a second shall include more distant stations.
1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the stations however, for units with separate radwaste systems, the submittal shall l
specify the releases of radioactive material from each unit.
l Amendment No.
6-19 I
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The Radioactive Effluent Release Report to be submitted by May 1 of each l year shall include an annual ~ summary of hourly meteorological data collected over the previous year.
This annual summary may be either in 1
the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in 1 1
the form of joint frequency distribution of wind speed, wind direction, e
6 and atmospheric stability This same report shall include an assessment of'the radiation doses due to the radioactive liquid and gaseous effluents releases from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 5.1-1) during the report f
period.
All assumptions used in making these. assessments, i.e.,
-specific activity, exposure time and location, shall be included in l
these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.
Approximate and conservative approximate methods j
are acceptable. Theassessmentofradiablondosesshallbeperformedin accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCH).
Acceptable methods for calculating the dose contr'.bution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.
1,' October 1977
'ihe Radioactive Effluent Release Report shal} include the following l information for each class of solid waste (in compliance with 10 CFR Part 61) shipped offsite during the report period I
6 In lieu of submission with the Radioactive Effluent Release Report, the l
licensee has the option of retaining this sunanary of required meteorological data onsite in a file that shall be provided to,the NRC upon request.
t lonendment No.
6-20
a.
container volume, b.
total curie quantity (specify whether determined by measurement or estimate),
c.
principal radionuclides (specify whether determined by measurement l
or estimate),
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source of waste and processing employed (e.g.,
dewatered spent resin, compacted dry waste, evaporator bottoms),
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type of container (e.g.,
LSA, Type A, Type B, Large Quantity), and t.
solidification agent or absorbent (e.g.,
cement, urea formaldehyde).
E.
ROUTINE REPORTING REOUIREMENTS l
1.
The results of the survelliance performed pursuant to Specifications 4.10.A and 4.10.B above will be included in the Radioactive Effluent Release Report to the extent required by Specification 6.9.1.6.
f In addition, this report shall include the information recorded pursuant to Specification 4.10.D above during the report period.
Basis l
The sampling and monitoring requirements specified in Specification 4.10.A and 4.10.B provide assurance that radioactis; materials released in liquid and gaseous wastes are properly controlled and monitored in conformance with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
These requirements provide the data for the licensee and the Commission to evaluate the performance of the plants relative to radioactive waste effluents released to the environment.
Specification 4.10.B excludes monitoring the turbine building ventilation exhaust since this release is expected to be a negligible release point. Many PWR reactors do not have turbine building enclosures. To be consistent in the requirement for Amendment No.
4.10-4
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l all PWR reactors, the monitoring of gaseous releases from the turbine building is not required.
Specification 4.10.D specifies the appropriate information to be recorded and maintained regarding offsite shipments of solid radioactive waste.
As referenced in Specification 4.10.E, reports on the quantities of liquid, gaseous and solid radioactive materials released from the site are furnished to the Commission in the Radioactive Effluent Release Report pursuant to Specification 6.9.1.6 and in conformance with USNRC Regulatory Guide 1.21, Revision 1.
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basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
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i Amendment No.
4.10-5
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Table 4.10-1 Radicactive Licuid Waste Samoline and Analvsis P ocram Table Notatien a.
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 systems background, that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observe. tion represents a *real' signal. The LLD shall be determined in accordance with the methodology and parameters in the CDCM.
It should be recognized that the LLD is defined as an a criori (before the fact) limit representing the capability of a measurement system and not as an a nesterieri (after the fact) limit for a particular
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measurement.
b.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.
(Steam Generators may be considered a batch release for reporting purposes during shutdown condition.)
c.
The principal gamma emitters for which the LLD specification applies exclusively are the following radienuclides:
Mn-54, Fe-59, Co-Sa, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141.
Other gamma peaks that are l
identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 6.9.1.6.
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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.
A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,
from a volume of a e.
system that has an input flow during the continuous release.
f.
When operational or other limitations preclude specific gamma radienuclide analysis in batch releases, the provisions of Regulatory Guide 1.21 (Revision 1), Appendix A, Section C.4 and Appendix A, Section B shall be followed.
For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD.
Under these gircumstances, the LLD may be increased in inverse proportion to the magnitude of the gamma yield (i.e.,
5 x.10/I, where I is the photon abundance expressed as a decimal fraction).
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Amendment No.
(Page 2 of 2)
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Table 4.10-3 Radioactive Caseous Waste Samoline and Analysis Precram Table Netatien a
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 systems background, that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observation represents a *real*
signal. The LLD shall be determined in accordance with the methodelogy and parameters in the CDCM.
It should be recognized that the LLD is defined as an a crieri (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.
b The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133 Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, "n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. Other gaz=ta peaks.
that are identifiable. together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Specification 6.9.1.6.
f If discharging via this pathway, sampling and. analysis shall also be performed following shutdown, startup, e
or a thermal power change exceeding 15 percent of rated power within one hour unless (1) analysis shows that the dose equivalent I-131 concentracion in the primary coolant has not increased by more than a factor of 3, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
d Radiation monitor sensitivity.
Grab sample can be used as alternative to continuous sampling.
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The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.9.B.l.a, 3.9.B.3.a and 3.9.B.4.a.
i Amendment No.
(Page 3 of 4) i
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l ATTACHME!7I' C SAFETY ASSESSMENT l
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l CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
INDIAN POINT UNIT NOS. 1&2 DOCKET NOS.50-003 & 50-247 SEPTEMBER, 1993 l~
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l September, 1993 Indian Point Units No. 1&2 Descriotion of Chance l
l NRC's final rule 57 Fed Reg. 39353 (August 31, 1992) amended regulations to l
reduce the regulatory burden on nuclear licensees.
10 CFR 50.36a was amended to change the reporting requirement for Radioactive Effluent Release Reports from semiannually to annually.
Indian Point Station Unit No. 1 Technical Specification 6.8 and 6.9 and Indian Point Station Unit No. 2 Technical Specification 6.9.1.6 requires that routine Radioactive Effluent Release Reports be submitted semiannually.
l It is proposed that the reporting period be changed to annually to comply with the amended 10 CFR 50.36a.
Basis For No Sicnificant Ha ards Consideration Determination The proposed change does not involve a significant hazards consideration because:
1.
There is no significant increase in the probability or consequences of an accident previously evaluated.
The proposed change is designed to conform the Indian Point Unit No. 1 (IPl) and Indian Point Unit No. 2 (IP2) Technical Specifications to the NRC regulation 10 CFR 50.36a.
The proposed action "will not reduce the protection of the public health and safety or the common defense and security" (57 Fed Reg. 39354).
The proposed change to the IPl and IP2 Technical Specifications is consistent with this intent in that it is designed to conform IPl and IP2 Technical Specifications with 10 CFR 50.36a and does not affect plant operation, plant systems, accident conditions or assumptions. The proposed change is to the frequency of a reporting requirement only and does not affect possible initiating events for accidents previously evaluated or any system functional requirements.
Therefore, the proposed change to the subject Technical Specifications cannot increase the probability or consequences of an accident previously evaluated.
2.
The possibility of a new or different kind of accident from any previously evaluated has not been created.
As stated above, the proposed change is administrative in nature.
The proposed change does not affect the reactor coolant pressure boundary or any other Plant system or structure, nor does it affect any system functional requirements or operability requirements. Consequently, no g
new failure modes are introduced as a result of the proposed change.
Therefore, the proposed change cannot initiate any new or different kind of accident.
3.
There has been no significant reduction in the margin of safety.
The proposed change is administrative in nature and does not affect the Updated Final Safety Analysis Report (UFSAR) design bases, accident assumptions, or Technical Specification Bases.
There is no change to effluent release limits, monitoring equipment or practices. Therefore, the proposed change does not result in a reduction in the margin of safety.