ML20035F244
| ML20035F244 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/14/1993 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20035F240 | List: |
| References | |
| NUDOCS 9304210073 | |
| Download: ML20035F244 (18) | |
Text
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'i ATTACHMENT 1 b
CONSUMERS POWER COMPANY i
-BIG ROCK POINT PLANT DOCKET 50-155 l
TECHNICAL SPECIFICATION CHANGE REQUEST l
AS PROPOSED PAGES i
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ADMINISTRATIVE CONTROLS l
6.3 PLANT STAFF OUALIFICATIONS i
6.3.1 Each member of the plant staff shall meet or exceed the minimum l
qualifications of ANSI N18.1-1971.for comparable positions.
6.3.2 Either the Chemistry and Health Physite Superintendent or the
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Radiation Protection Supervisor shall-meet or exceed the
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qualifications of Regulatory Guide 1.8, September 1975.
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6.3.3 The On-call Technical Advisor (OTA) shall have a bachelorf s degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for
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transients and accidents.
6.3.4 The Operations Superintendent shall hold a Senior Reactor Operator License. The Operations Superintendent shall be responsible for -
j directing the activities of licensed operators. He shall meet the i
other requirements of Section 6.3.1 (as applicable to Operations Manager in ANSI N18.1).
6.4 TRAINING 6.4.1 A retraining and replacement training program for the~ plant staff shall be maintained and implemented and shall meet or exceed the requirements and recommendations of' Section 5.5 of ANSI N18.1-1971 l
and 10 CFR 55.
6.4.2 A fire brigade training program shall be maintained and implemented and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire Brigade training drills shall be held at least quarterly.
3For the purpose of this section, " Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following:
(a) Formal schooling in science engineering, or (b) operational or technical experience / training in nuclear i
l power.
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AS PROPOSED
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i' ADMINISTRATIVE CONTROLS l
1 6.10.2 (Contd) l k.
Records for environmental qualifications which are covered l
i under the provisions of 10 CFR 50.49.
i Recordgf training and qualification for members of the Plant 1.
Staff.
Records of reactor tests and experiments.(a) m.
6.11 RADIATION PROTECTION PROGRAM i
Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA In lieu of the " control device" or " alarm signal" required by 6.12.1 Paragraph 20.1601(a) of 10 CFR Part 20, each high radiation area
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in which the intensity of radiation is less than 1000 mrem /h at
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from the radiation source or from any surface which the radiation l
penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by the use of a Radiation Work Permit (RWP). Radiation protection qualified personnel or personnel continuously escorted by radiation protection qualified personnel may be exempt from working under an RWP during the performance of their assigned ~ radiation protection duties in high radiation areas with exposure rates of less than 1000 mrem /h, provided they are otherwise following plant radiation protection procedures for entry into such high i
l radiation areas. Any individual or group of individuals permitted l
to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, or b.
A radiation monitoring + vice which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been -
established and personnel have been made knowledgeable of them, or (a) Movement of items 6.10.21 and m from section 6.10.1 increased the length of time for which records must be retained from five years to the duration of the operating license. Since these changes in record keeping will begin on or about January 1, 1984, records of these two types created after December 31, 1978 will be retained for the duration of the~ operating license.
Retention for the duration of the operating license will not be required for records of thase two types created before January 1,1979.
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ADMINISTRATIVE CONTROLS 6.12.1 (Contd) c.
A radiation protection qualified individual (e.g., Health Physics Technician) with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area, and shall perform periodic radiation surveillance as specified by the Chemistry and Radiation Protection Supervisor in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mrem /h at 30 cm (12 in) from the radiation source or from any surface /
from which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as l
closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mrem /h that.are located within
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large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 ENVIRONMENTAL 00ALIFICATION (Deleted) i 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Changes to the PCP shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:
a.
Sufficiently detailed information to support the rationale for the change; b.
A determination that the change did not reduce the overall l
conformance of the solidified waste product to existing l
criteria for solid wastes; and-c.
Documentation of the fact that the change has been reviewed f
and approved by the responsible Nuclear Operations Department per CPC 2A (Quality Assurance Program).
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AS PROPCSED 1
13.1.2.
L10VID EFFLUENTS CONCENTRATION 13.1.2.1 The concentration of radioactive material released in liquid effluents from the site to areas at or beyond the site boundary (see Figure 2.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table 2, Column 2 for radionuclides
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other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 1.4 x 10 microcuries/ml total activity.
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4 APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released in a.
liquid effluents from the site to areas at or beyond the site boundary (see Figure 2.1) exceeding the above limits, upon discovery promptly restore the concentration to within the above limits.
13.1.2.2 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 13-3.
13.1.2.3 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 13.1.2.1.
BASES FOR 13.1.2.1 - LIOUID EFFLUENT CONCENTRATIONS This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
This limitation provides additional assurance that the
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levels of radioactive materials in bodies of water in unrestricted areas will result in exposures within (1) the Section II.A. design objectives of Appendix I,10 CFR Part 50, to a member of the public, and (2) the limits of 10 CFR Part 20.1301(e) to the population.
The concentration limit for
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dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its effluent concentration in air
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(submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICPR) Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L A, " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, J K. " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
133 AS PROPOSED
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13.1.3 GASE0US EFFLUENTS DOSE RATE 13.1.3.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary (see Figure 2.1) shall be limited to the following:
7 For noble gases: Less than or equal to 500 mrems/yr to the
'otal body and less than or equal to 3000 mrems/yr to the.
, kin, and b.
For iodine-131, for iodine-133, for tritium and for all j
radionuclides in particulate form with half lives greater than 8 days:
Less than or equal to 1500 mrems/yr to any organ, j
APPLICABILITY: At all times.
I ACTION:
i With the dose rate averaged over a period cf one hour a.
exceeding the above limits, upon discovery promptly restore l
the release rate to within the above limit (s).
13.1.3.2 The dose rate due to noble gases'~in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM.
13.1.3.3 The dose rate due to iodine-131, iodine-133, tritium and all l
radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing -
analyses in accordance with the sampling and analysis program i
specified in Table 13-3.
BASES FOR 13.1.3.1 - GASEOUS EFFtVENT DOSE RATE This specification is provided to allow the Licensee operational flexibility
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in meeting the limits of 10 CFR 50, Appendix 1.
The dose rates of this
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specification are higher then the implied dose rates of 10 CFR 20, Appendix B,
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Table 2, Column 1 Effluent Concentrations for Members of the Public. However,
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the Licensee is expected to implement the ALARA philosophy for gaseous effluents
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to ensure doses to the public at and beyond the site boundary are minimized
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and less than the annual doses of 10 CFR 50, Appendix I.
For members of the
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public who may at times be within the site boundary, the occupancy of that
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member of the public will usually be sufficiently low to compensate for any
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increase in dose rate'due to atmospheric dispersion above that for the site
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boundary. Examples of calculations for such members of the public, with the appropriate occupancy factors, shall be given in the'00CM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a member of the public at or beyond -
the site boundary to less than or equal to 500 mrems/yr to the total-body or 134
'AS PROPOSED-
BASES FOR 13.1.3.1 - GASE0US EFFLUENT DOSE RATE (Contd) or to less than or equal te W rems /hr to the skin. These release rate
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also restrict, at all times, Se corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/yr.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L A " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, J K, " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-2J5 (June 1975).
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l AS PROPOSED I
13.1.5 SOLID RADI0 ACTIVE WASTE 4
13.1.5.1 The solid radwaste system shall be used in accordance with a Process Control Program to process wet radioactive wastes to meet i
shipping and burial ground requirements.
APPLICABILITY: At all times.
ACTION:
With the provisions of the Process Control Program not a.
satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.
BASES FOR 13.1.5 - SOLIO RADI0 ACTIVE WASTE The process parameters included in establishing the Process Control Program may include, but are not limited to, waste type, waste pH, waste / liquid /
solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents and mixing and curing times.
13.1.6 TOTAL DOSE 13.1.6.1 The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
i With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 13.1.4.1.a, 13.1.4.1.b, 13.1.4.2.a 13.1.4.2.b, 13.1.4.3.a, or 13.1.4.3.b, calculations should be made including direct radiation contributions from the reactor unit and from outside storage tanks to determine whether the above limits of Specification 13.1.6.1 have been exceeded.
If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective actici to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part i
20.2203(4), shall include an analysis that estimates the radiation
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to a member of the )ublic from uranium fuel cycle exposure (dose)ing all effluent pataways and direct radiation, for sources, includ l
the calendar year that includes the release (s) covered by this It shall also describe levels of radiation and report.
i concentrations of radi, active material involved and the cause of the exposure levels or concentrations.
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142 AS PROPOSED l
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13.1.6.2 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specification 13.1.4.4 and in accordance with the methodology and parameters in the ODCM.
13.1.6.3 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.
This requirement is applicable only under conditions set forth in Specification 13.1.6.1.
BASES FOR 13.1.6.1 - TOTAL _ DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The s secification requires the preparation and submittal of a Special Report wienever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. The Special Report will describe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR Part 190 limits. For the pur>oses of the Special Report, it may be assumed that the dose commitment to tie member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 mi must be considered.
If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR 20.2203(4), is considered to be a
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timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications and an individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
143 AS PROPOSED
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ATTACHMENT 2 CONSUMERS POWER COMPANY-l BIG ROCK POINT PLANT DOCKET 50-155 j
i TECHNICAL SPECIFICATION ~ CHANGE REQUEST
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ADMlWISTRATIVE COWTR0tJ i
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6.3 PLANT STAFF QUA1.lFICATIONS 6.3.1 Each member of the plant staf f shall meet or exceed the minieue qualifications of ANSI N18.1-1971 for comparable positions.
(
Either the Chemistry and Health Fhysics Superintendent or the Ghemistry-6.3.2 M Radiation Protection Superv,sor shall meet or exceef the i
qualifications of Regulatory cuide 1.8, September 1975.
The on-call Technical Advisor (OTA) shall have a bachelor's degree i
6.3.3 or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
shall hold a Senior Reactor Operator I
The Operations Superintendent 6.3.4 The Operations Superintendent shall be responsible for License.
He shall meet the directing the activities of licensed operators.
I other requirements of Section 6.3.1 (as applicable to Operations Manager in ANSI W18.1).
6.4 TRAlWIWC A retraining and replacteent training program for the plant staf f l
6.4.1 shall be maintained and implemented and shall meet or exceed the requirements and reconcendations of Section 5.5 of Axs! N18.1-1971 and 10 cra 55.
A fire brigade training program shall be maintained and implemented 6.4.2 and shall, as practicable, zeet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire Brigade training dri!!s shall be held at least quarterly.
For the purpose of this section, " Equivalent," as utilized in Regulatory I
cuide 1.8 for the bachelor's degree requirement, may be met with four years (a) Formal schooling in science of any one or combination of the following:
engineering, or (b) operational or technical experience / training in nuclear power.
74 Amendment 107 February 19, 1992 TS SECTICH 10
ADMlWISTRATIVs COWTROLS 6.10.2 (Cootd)
Records for environmental qualifications which are covered k.
under the provisions of 10 CFR 50.49.
Recordgf training and qualification for members of the Plant 1.
Staff.
Records of reactor tests and esperiments.(a) s.
6.11 RADI ATION PROTECTION PROCRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation esposure.
6.12 HICH RADIATION AREA yp f60/[q) pg 47 3Od 6.12.1 In lieu of the " control device" or "alare signal" equired by Paragraph &#Cis of 10 CFR Part 20, each high radiation area in which the intensity of radiation is less - than 1000 " A ja,4.from the radiation source or from any surface which the radiation penetrates shall be barricaded and conepicuously posted as a high radiation area and entrance thereto shall be controlled by the use of a Radiation Work Permit (RWP). Radiation _ protection qualified ~ personnel or personnel continuously escorted by radiation protection qualified personnel may be exempt from working under an kWP during the performance
(
of their_ assigned radiation protection duties in high radiation areas with esposure rates of less than 1000 rovided they are otherwise following plant radiation protection proce res for entry into such high radiation areas. Any individual or group, f individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followings
.d g A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, or b.
A radiation monitoring device which' continuously integrates the radiation dose rate la the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made af ter the dose rate levels in the area have been estabiinhed and personnel have been~ made knowledgeable of them, or (a) Movement of itens 6.10.2 'I and a fros section 6.10.1 increased the length of time for which records must be retained from five years to.the duration of the operating license.
Since these changes in record keeping will begin on or about January 1,1984, records of these two types created after December 31, 1978 vill be retained for the duration of the operating license.
Retention for the duration of the operating license will not be required for records of these two types created before January 1,1979.
k 89 Ar,endment 107 February 19, 1992 l
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ADM1WI$TRAT!YC COWT101.5 4
1 6.12.1 (Contd)
A radiatloa protection gustified individual (e.g., Eealth Physics Technician) with a radiation dose rate moniterf ta device, who is c.
responsible for providing positive control over the activities within the area, and shall perform periodic radiation surveillance as specified by the Chemistry and Radiatloa Protection Supervisor in the I
RWP.
4 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 ht O. US h..) from the radiation source or free any surface
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e7 MNG [s f rom which the radiation penetrates shall be provided with locked f
doors to prevent unauthorized entry, and the keys shall be maintained pg f3 under the administrative control of the shift supervisor on duty Doors shall renais locked except and/or hestth physics supervision.
during periods e f access by personnel under an approved gWP which shall specify the dose rate levels in the Ismediate work areas and the In lieu of raximum allowable stay time for individuals in that area.
the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous survelliance may be made by personnel qualified, in radiation protection procedures to provide positive expor.ure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with r.diation
(
levels of greater than 1000 mehr t t are located withis large areas where no enclosure exists for purposes of locking, and no eactosure can be reasonably constructed around the individual areas, them that individual area shall be barricaded, conspicuously posted, and a flashing 11t e shall h
be activated as a warning device.
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6.13 EWVIRONMENTAL QUAI.IFICATION (Deleted) 6.14 PROCESS CONTROL PROCRAM (PCFl 6.14.1 Changes to the PCP shall be subeltted to the Commissies in the Sesiannual Radioactive Effluent Release Report for the period in which the change (s) was made ef fective. This submittal shall containt sufficiently detailed information to support the rationale for a.
the changel A determination that the change did not reduce the overall b.
conformance of the solidified waste product to esisting criteria for solid wastest and Documentation of the f act that the change has been reviewed c.
and approved by the responsible Nuclear' Operations Department per CPC 2A (Quality Assurance Program).
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90 Amendment 107 February 19, 1992
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f LIQUID EFFLUENTS CONCFJff1ATION i
13.1.2.
The concentration of radioactive material released le 11gvid l
13.1.2.1 ef fluents from the site to areas at er beyond the site boundary (see Figure 2.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendia 3,
'l".'.;. IT,, Column 1 for radlonuclides other than dissolved or entrained noble,ases. For dissolved or i
J entraingd noble gases, the concentrationshall be limited to
[
10'2-microcuries/mi total activity. L 7g *f_,,
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A.PPLICABILITY: At a!! times.
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With the concentration of radioactive material released la 11guld effluents from the site to areas at or beyond the site a.
boundary (see Figure 2.1) exceeding the above IIsits, upos discovery promptly restore the concentration to within the
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above limits.
Radioactive liquid vastes shall be sempted and analyted according l
13.1.2.2 to the sampling and analysis program of Table 13-3.
J The results of the radioactivity analyses shall be used in e
l 13.1.2.3 accordance with the methodology and parameters in the ODCN to assure that the concentrations at the point of release are l
maintained within the limits of Specification 13.1.2.1.
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BASES FOR 13.1.2.1 - LIQUID EFFLUDff CONCEWT1LATIONS
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-This specification is provided to ensure that the concentration of radioactive sacertals released in 11guld vaste ef fluents to unrestricted areas will ne less than the concentration levels specified in 10 CFR Part 20, Appendia 8, This limitation provides additional assurance that the 7 m 2 _T.t!, &, column 2. levels of radioactive materials in bodies of veter in unrest result in exposures withia (1) the 3ection II.A. design objectives of N[hppendiz 1, 70 CFR Part 50, to a member of the public, The concentration limit for 10 CFR Part M.!O) to the population.
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dissolved or entrained noble gases 'is based upon the assumption that E
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the controlling radioisotope and its " -(submersion) was converted to I
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The required detection capabilities for' radioactive materists la 11guld waste saroptes are tabulated la terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD and other detection limits can be fo Prrcedures Manual, HASL-300 (revised annually), Currie, L A, " Limits for Qualitative Detection and Quantitative Determination - Applicati Radiochemistry," Mat Ches Limits for Radionnalytical Counting Techniques," Atlantic tichfield Ianford Company Report ARH-SA-215_ (June 1975).
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Amendment 107 February 19, 1992 TS SECTION 13
13.1.3 CASE 001 EFFLUnrT100Sg LATE i
fte dose rate due to radleactive asterials released la gaseems i
13.1.3.1 ef fluents from the site to areas at and beyond the site boundary (see Figure 2.1) shall be tialted to the followlagt j
For noble gasest Less than or equal to 500 aress/yr to the f
a.
total body and less than or egual to 3000 areas /yr to the skin, and 4
For lodine-131, for iodine-133, for tritius and for att I
b.
radionuclides in particulate form with half lives greater than Less thaa or equal to 1500 aress/yr to any organ.
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3 g days:
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APPLICABILITY: At all times.
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i ACTI0d:
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With the dose rate averaged over a period of one hour 1
s.
exceeding the above limits, upon discovery promptly restore 2
the release rate to within the above limit (s).
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The dose rate due to noble gases in gaseous ef fluents shall be 13.1.3.2 determined to be within the above limits in accordance with the i
sethodolog;y and parameters in the ODCM.
The dose rate due to iodine-131, iodine-133, tritium and all 13.1.3.3 radionuclides in particulate form with half IIves greater than 8 days in gaseous effluents shall be determined to be within the l
above limits in accordance with the methodology and parameters in i
the ODCM by obtaining representative samples and perforslag l
analysas in accordance with the sampling and analysis progras l
specified in Table 13-3.
BASES FOR 13.1.3.1 - CASE 005 EFFLUENT DOSE RATE
' This spe
- ication is vided to sure that t dose at any ti at and I
s beyond e stTE Y from eous efflu from all units the site vil e within t annual do limits of If F1 Part 20 to a stricted a as.
annual do limits are e doses ass sated with the co entrations f 0 CFR Part 0, Appendl
, Table 11, uan 1.
These 11 te provide reasonab assurance at radioactiv material discharg te gaseous (fluents will n result la e exposure of
=>=h+r of the pu e la an unr stricted either wit a or outside t site boundary, t annual avers e e centration exceeding the 1 its specified in pendia 8, Ta e II of are 0 CFR Par 0 (10 CPR Part
.106(b)). For me rs of the p lic who.
at times be sthin the SITE DARY, the occupa y of that mes r of the oblic will vally be suffici tly low to compen a for any (ne ase in t at spheric diffusion actor above that r the site bou ary. [ Examples of
~ calculations for such members of the public, with the appropriate occupancy f actors, shall be given in the ODCM. The specified release rate limits restrict, at all r.ines, the corresponding garna and beta dose rates above background to a n.aber of the public at or beyond the site boundary to less 134 bWIE M IEi!W4<-f u> 1M S f.4.71ord Amendment 107 February 19, 1992 oa # q,f-T 774pr TS SECTION 13
(Contd) bases Fog 13.1.3.1 - CASE 00$ EFFLUEWT 00$t R. Aft l to than or egust to 500 areas /yr to the total body or to less than er equaThese 3000 arems/hr to the skin.
hild via the times, the corresponding thyroid dose rate above background to a c
.an er equal to 1500 areas /yr.
inhalation pathway to less The required detection capab(11 ties for radioactive materists in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD and other detection 11alts can b Procedures Manual, NASL-300 (revised annually) Currie, L A " Limits for Qualitative Detectlon and Quantitative Determination - Application toand Eartw
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40, 586-93 (1968),
Radiochemistry," Anal ChesLimits for Radicanalytical Counting Techniques,"
Company Report A1H-SA-215 (June 1975).
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135
(
Amendoest 107 February 19, 1592 TS SECTION 13
i 13.1.5 sOtt D RAD 10ACflVE WAST 1 13.1.5.1 The solid radwaste system shall be used is accordance with a Process Control Program to process wet radioactive vastes to east shipping and burial ground require =nts.
APPLICABILITY At all times.
ACTIOkt With the provisions of the Process Control Program not
.a.
satisfied, suspend shipments of defectively processed or defectively packaged so11d radloactive vastes from the site.
BASES FOR 13.1.5 - SOLID RADIOACTIVE WASTE The process parameters included in establishing the Process Control Progras may include, but are not limited to, waste type, vaste pH, vaste/ liquid /
solidification agent / catalyst ratios, waste oil content, vaste principal j
chemical constituents and mixing and curing times.
13.1.6 TOTAL Dost 13.1.6.1 The annual (calendar year) dose or dose coenitment to any member of the public due to releases of radicactivity and to radiation froe uranius fuel cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ, except the thyroid, which shall be limited to less than or equel to 75 areas.
APPLICABILITY: At all times.
ACTIoW1 With the calculated doses from the release of radioactive materials l
in 11guld or gaseous effluents exceeding twice the !!alts of S pe c i ficati on s 13.1.4.1. a. 13.1.4.1.b, 13.1.4. 2.a, 13.1.4. 2.b, 13.1.4.3.a. or 13.1.4.3.b, calculations should be made including direct radiation contributions from the reactor unit and free outside storage tanks to determine whether the above limits of specification 13.1.6.1 have been exceeded. If such is the case, prepare and subelt to the Commission within 30 days, e special Report that defines the corrective action to be taken to reduce subseguest releases to prevent recurrence of. exceeding the above limits and includes the schedule for achieving conformace with the This spectal Report, as defined in le crt Part M ' po3 M_above !! sits.
- L'MS, shall include an analysis that estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources, including all ef fluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved and the cause of the esposure levels or concentrations.
142
(
Amendment 107 February 19,1992 TS SECTION 13 i
i i
i i
i 13.1.6.2 Cumulative deso contributions froe liquid cad gase:us effie:
4 Its shall be determined la accordance with specification 13.i.4.6 and i
la accordance with the methodology and parameters in the 00CN.
13.1.6.3 Cumulative dose contributions frera direct radiation from the reactor units and from radweste storage tanks shall be determined l
l In accordance with the methodology and parameters in the 000t.
i l
This requirement is app!! cable only under conditions sat forth in Specification 13.1.6.1.
l B ASES FOR 13.1.6.1 - TOTAt. DOSE This specification is provided to meet the dose limitations of 40 Cft Part 190 l
The that have been incorporated into 10 CFR Fart 20 by 46 FR 18525.
4 specification requires the preparation and submittal of a Special Report l
whenever the calculated doses from plant generated radioactive affluents and 4
direct radiation exceed 25 areas to the total body or any organ, eacept the l
m thyroid, which shall be limited to less than or equal to 75 areas.
Special Report will describe a course of action that should result la the limitation of the annual dose to a member of the public to within the 40 CFE 190 timits. For the purposes of the special Report, it may be assumed i
Part the dose commitment to the member of the public free other uranium fuel that cycle sources is negligible, with the exception that dose contributions from j
other nuclear fuel cycle f acilities at the same site or within a radius of 5 mi must be considered.
If the dose to any member of the public is estimated
)
te exceed the requirements of 40 *,FR Part 190, the Special Report with a request for a variance (provided the release conditions resulting la vlotation
('
of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFE Part 190.11 and 10 CFR %is considered to be a timely request and fulfills the requirements of 40 CF Part 190 until NEC staff action is completed. N variance only reistes o the !!alts of 40 Crt 190 and does not apply la any way to the other re of rements for dose Part limitation of 10 CFR Part 20, as addressed in Specifications and sa individual is not considered a member of the pubtle during any pe lod (a which he/she is engaged in carrying out any operation that is part of he nuclear fuel cycle.
- # gosh 143-(
Amendment 101 February 19, 1992
. TS SECTION 13
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