ML20034G420
| ML20034G420 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/04/1993 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20034G416 | List: |
| References | |
| NUDOCS 9303090488 | |
| Download: ML20034G420 (17) | |
Text
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l ATTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 TECHNICAL SPECIFICATION CHANGE REQUEST AS PROPOSED PAGES 9303090488 930304 PDR ADOCK 05000155 P
PDR L
ADMINISTRATIVE CONTROLS i
5.3 PLANT STAFF OVALIFICATIONS 6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.3.2 Either the Chemistry and Health Physics 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.
6.3.3 The On-call Technical Advisor (OTA) shall have a bachelor's degree 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.
6.3.4 The Operations Superintendent shall hold a Senior Reactor Operator License.
The Operations Superintendent shall be responsible for directing the activities of licensed operators. He shall meet the 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 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.
s For 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 power.
74 l
AS PROPOSED
ADMINISTRATIVE CONTROLS 6.10.2 (Contd) k.
Records for environmental qualifications which are covered under the provisions of 10 CFR 50.49.
1.
Recordg'9f training and qualification for members of the Plant Staff.
Records of reactor tests and experiments.(a) m.
6.11 RADIATION PROTECTION PROGRAM 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 AR M
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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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j 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 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 radiation areas. Any individual or group of individuals permitted 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 device 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 l
(a) Movement of items 6.10.21 and m from section 6.10.1 increased the length of l
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.
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Retention for the duration of the operating license will not be required for records of these two types created before January 1, 1979.
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ADMINISTRATIVE CONTROLS t
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.
j 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 i
specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of i
the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide l
positive exposure control over the activities 'eing performed within j
o the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mrem /h that are located within
/
large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual
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areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 ENVIRONMENTAL 00AtlFICAT10N (Deleted) 6.14 PROCESS CONTROL PROGRAM (PCP) l 6.14.1 Changes to the PCP shall be submitted to the Connission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This -submittal shall contain:
I a.
Sufficiently detailed information to support the rationale for l
the change; b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the change has been reviewed and approved by the responsible Nuclear Operations Department l
per CPC 2A (Quality Assurance Program).
90 AS PROPOSED l
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' 13.1.2.
LIOUID EFFLUENTS CONCENTRATION 13.1.2.1 The concentration of radioactive m4mial 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
/
other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to i
1.4 x 10' microcuries/ml total activity.
/
APPllCABILITY: At e.11 times.
I 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.
i 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 te used in accordance with the methodology and pararneters 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. JUENT CONCENTRATIONS This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to unrestricted areas will be i
less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
This limitation provides additional assurance that the
/
levels of radioactive materials in bodies of water in unrestricted areas will result in exposures within (1) the Section II.A. design objectives of J
Appendix I,10 CFR Part 50, to a member of the public, and (2) the limits of i
l 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 l
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 Qualitati';a Detection and Quantitative Determination - Application to l
Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, J K. " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARil-SA-215 (June 1975).
133 AS PROPOSED i
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13.1.3 GASEOUS 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:
a.
For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.
For iodine-131, for iodine-133, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate averaged over a period of one hour a.
exceeding the above limits, upon discovery promptly restore 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 ODCM.
13.1.3.3 The dose rate due to iodine-131, iodine-133, tritium and all
]
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 i
the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 13-3.
BASES FOR 13.1.3.1 - GASE0US EFFLUENT DOSE RATE This specification is provided to allow the Licensee operational fleKhility
/
in meeting the limits of 10 CFR 50, Appendix I.
The dose rate" 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 ' a Public. However,
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the Licensee is expected to implement the ALARA philosop / or gaseous effluents
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f 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 1.
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 ODCM. 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 - GASEOUS EFFLUENT DOSE RATE (Contd) or to less than or equal to 3000 mrems/hr to the skin. These release rate
/
also restrict, at all times, the 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-215 (June 1975).
135 AS PROPOSED
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'13.1.5 SOLID RADI0 ACTIVE WASTE j
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 shipping and burial ground requirements.
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1 APPLICABILITY: At all times.
ACTION:
I 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 - SOLID RADI0 ACTIVE WASTE t
The process parameters included in establishing the Process Control Program may include, but are not limited to, waste type, waste pH, waste / liquid /
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solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents and mixing and curing times.
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13.1.6 TOTAL DOSE 13.1.6.1 The annual (calendar year) dose or dose commitment to any member of 2
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:
With the calculated doses from the release of radioactive materials 1
in liquid or gaseous effluents exceeding twice the limit's of
{
Specifications 13.1.4.1.a,13.1.4.1.b, 13.1.4.2.a 13.1.4.2.b, l
13.1.4.3.a, or 13.1.4.3.b, calculations should be made including i
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, arepare and submit to the Commission within 30 days, a Special le) ort that defines the corrective action to be taken to reduce su) sequent 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 20.2203(4), shall include an analysis that estimates the radiation
/
exposure (dose) to a member of the aublic from uranium fuel cycle sources, including all effluent pat 1 ways 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 exposure levels or concentrations.
142 AS PROPOSED
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 i
in accordance with the methodology and parameters in the 00CM.
This requirement is applicable only under conditions set forth in Specification 13.1.6.1.
i BASES FOR 13.1.6.1 - TOTAL DOSE l
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 i
saecification requires the preparation and submittal of a Special Report wiencver the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, exce)t the thyroid, which shall be limited to less than or equal to 75 mrems. T 1e Special Report will describe a course of action that should result in the i
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 S)ecial Report, it may be assumed that the dose commitment to tie member of tie 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
/
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 l
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.
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143 AS PROPOSED
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i ATTACHMENT 2 i
l CONSUMERS POWER COMPAliY BIG ROCK POINT-PLANT DOCKET 50-155 l
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TECHNICAL SPECIFICATION CHANGE REQUEST I
MARKED UP PAGES i
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1 ADMtWISTRATIVE COWu01.8
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f 6.3 pl.AWT STAFF QUA1.tFICATIONS Each member of the plant staf f shall meet or escoed the minious l
6.3.1 qualifications of AWS1 W18.1-1971 for comparable positions.
1 Either the Chemistry and Health Physics Superintendent or the O.._:--
6.3.2 eed-Radiation Protection Supervisor shall meet or exceef the qualifications of tegulatory Cuide 1.8, September 1915.
The On-call Technical Advisor (OTA) shall have a bachelor's degree 6.3.3 or equivalent in a scientific or engineering discipline with specific t raining in plant design, and response and analysis of the plant for transients and accidents.
6.3.4 The Operations Superintendent shall hold a Senior Reactor Operator License. The Operations Superintendent shall be responsible for He shall meet the directing the activities of licensed operators.
other requirements of Section 6.3.1 (as applicable to Operations Hanager in ANSI W18.1).
j 6.4 TRAINtNC 6.4.1 A retraining and replacement training program for the plant staff shall be maintained and implemented and shall acet or exceed the requirements and recose.endations of Section 5.5 of ANSI W18.1-1971 and 10 CFR 55.
A fire brigade training program shall be maintained and implemented i
6.4.2 and shall, as practicable, acet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire Brigade training drille shall be held at least quarterly.
]
i For the purpose of this section, " Equivalent," as utilized in gegulatory l
I J
Cuide 1.8 for the bachelor's degree requirement, say be met with four years of any one or combination of the following:
(a) formal schooting in science engineering, or (b) operational or technical experience / training in nuclear power.
74 Amende,ent 107 February 19, 1992 TS SECTION 10
ADMiWISTRAT!ift COWTROLS 6.10.2 (comed)
Records for environmental qualifications which are covered k.
under the provisions of 10 Crt 50.49.
Recordgajf training and qualification for members of the Plant 1.
Staff.
Records of reactor tests and experiments.(a) n.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 Crt, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HICH RADIATION AREA y,0, f 60/ [q) gg g7 3Od 6.12.1 In lieu of the " control device" or " alarm signal" equired by Paragraph 46v$6cMi, of 10 CFR Part 20, each high radiation area in which the intensity of radiation is less than 1000 * " "
imv) from the radiation source or from any surface which the radiation penetrates shall be barrie.aded and conspicuously posted as a high radiation area and entrance thereto shall be contro11ed by the use of a Radiation Work, Permit (RWP). Radiation protection qualified personnel or personnel continuously escorted by radiation protection qualified personnet may be exempt f rom working under an RWP during the performance
{
of their assigned radiation protection duties in high radiation areas with exposure rates of less than 1000 rovided they are otherwise following plant radiation protection proce res for entry into such high radiation areas. Any individual or group f Individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followingt dgg A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, or b.
A radiation monitoring device which continuously lategrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels is the area have been established and personnel have been made nmovledgeable of them, or (a) Movement of items 6.10.21 and a from section 6.10.1 increased the length of time for which records must be retained from five years to the duration of the operating license.
Since these changes in record keeping will begin on or about January 1,1984, records of these two types created after December 31, 1978 will be retained for the duration of the operating license.
Retention for the duration of the operating license will not be required for records of these two types created before January 1,1979.
(
89 Amendment 107 February 19, 1992
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e e
ADMIWI$TRATIYt COWTROLS 6.12.1 (Contd)
A radiation protection guallfled individual (e.g., Bealth Physics Technician) with a radiation dose rete monitoring device, who is c.
responsible for providing positive control over the activities withis the area, and shall perform periodic radiation survelitsace as specified by the Chemistry and Radiation Protection Supervisor in the LWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 g!:..;. O. US *.3 from the radiation source or from any surface MW//* #7 from which the radiation penetrates shall be provided vir.h locked pm [z doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty f
and/or health physics supervision. Dcors shall remala locked except during periods of access by personniet under an approved RWP which shall specify the dose rate levels in the immediate work areas and the In lieu of maximum allevable stay time for individuals in that area.
the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualifie4, in radiation protection procedures to provide positive esposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation
[
levels of greater than 1000 se/ir t at are located withis large areas where no enclosure exists for purposes of locking, and no emelosure can be
(
reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuously posted, and a flashing light shall I
be activated as a warning device.
/
6.13 ENVIROKHENTAL QUALIFICATION (Deleted) 6.14 PROCESS CONTROL PROCRAM (PCP_)
6.14.1 Ch. ages to the Pcp shall be submitted to the Commisslom la the Semiannual Radioactive Effluent telease Report for the period in which the change (s) was made effective. This submittal shall contains Sufficiently detailed information to support the rationale for s.
the changel A determinat. ion that the change did not reduce the overall 1
b.
conformance of the solidified waste product to existing l
criteria for solid wastes; 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).
(
90 Amendment 101 February 19, 1992
lj 4
LIQU10 EFFLUENTS CONCEN M ATION 13.1.2
}
13.1.2.1 The concentration of radioactive material released la 1tgeld ef f tvents from the site to areas at or beyond the site beendary (see Figure 2.1) shall be limited to the concentrations specified l
in 10 CFR Part 24, Appendia 8, ".Lt.
2., Coluna 2 for rad;,onectides other than dissolved or entrained noble
,ases. For dissolved or entrain h
t tion shall be fielted to
-2 ; Tgd noble gases, t e concen rab,rocuries/si total l
mic 34 L l
/466g,-#
APPLICABILITY At all times.
ACTIOWs With the concentration of radioactive material released la a.
11guld efftvents from the site to areas at or beyond the site 4
boundary (see Figure 2.1) exceeding the above !! nits, upoa discovery promptly restore the concentration to within the j
above limits.
l 13.1.2.2 Radioactive liquid vastes shall be sampled and analyzed according 4
1 to the sampling and analysis program of Table 13-3.
2 j
13.1.2.3 The results of the radioactivity analyses shat! be used la accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are
,I maintained within the limits of Specification 13.1.2.1.
BASES Foa 13.1.2.1 - LIQUID EFFLUENT CONCENTRATIONS
{
l This specificatioe is provided to ensure that the concentration of radioactive materials released in liquid wasta ef fluents to unrestricted areas will be l
1ess than the concentration levels specified in 10 CFR Part 20, Appendix g, This limitation provides additional assurance that the
-7m 2. -Td!. 30, Column 2.
levels of radioactive materials in bodies of water in unrestricted areas will 1
result in exposures within (1) the Section II.A. design objectives of Jg.l'30I[MAppendix 1,10 CFR Part 50, to a member of the public l
~ 10 CFR Part M.10N to the population.
He concentration !! alt for j
dissolved or entrained noble gases is based upon the assumption that Ee-135 is i
^_..L M7 Q the controlling radioisotope and its " i
.";.i.*1"-
1.-
/g i+ air (submersion) was converted to an egulvstent concentration l f/hafu y tu
, w. a..,.r u t w--
-- 2d 1_
2 = e; ;g dNtfa%
r g
P-et e" he m'* ) ??' ' + ",
he required detection capabilities for radioactive materf ats in liquid vasta samples are tabulated in terms of the lower limits of detection (LLDs).
1 1
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 l
Qualitative Detection and Quantitative Determination - Application to 1
Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwe11, J K. " Detection Limits for Radioanalytici Counting Techniques," Atlantic tichfield ganford Company Report ARH-SA-212 (June 1975).
133
(
Amendment 107 l
February 19, 1992 4
TS SECTION 13
o i
BASES FOR 13.1.3.1 - CASE 00$ EFFLUEWT DOSE RAtt (Con h
q al te than or equal to 500 arems/yr to the total body or to less t an or e uThe hild via the 3000 aress/hr to the skin.
times, the corresponding thyroid dose rate above background to a c inhalation pathway to less than or equal to 1500 arems/yr.
i The required detection capabilities for radioactive materials in gaseous wa (LLDs).
samples are tabulated in terms of the lower limits of detection Detailed discussion of the LLD and other detection limits l
2 Procedures Manual, HASL-30_0 (revised annually) Currie, L A, " Limits Qualitative Detection and Quantitative Determination - Application to i
40, 586-93 (1968), and Hartwell, J K, " Detect on
/
Radiochemistry," Anal ChemLimits for Radioanalytical Counting Techni Company Report AH-SA-215 (June 1975).
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135
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Amendment 107 February 19, 1992 TS SECTION 13
?
g 13.1.5 SOLID RADICACTIVg VASTS 13.1.5.1 The solid radweste system shall be used la accordance with e Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
APPLICABILITYt At all times.
j i
ACTIOWs i
s.
With the provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive vastes from the site.
BASES FOR 13.1.5 - SOLID RADI0 ACTIVE WASTE The process parameters included in establishing the Process Control Progras may include, but are not limited to, vaste type, vaste pH, vaste/ liquid /
solidification agent / catalyst ratios, vaste oil content, waste principal chemical constituents and mixing and curing times.
j 13.1.6 TOTAL Dost 13.1.6.1 The annual (calendar year) dose or dose commitment to any member of 1
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 areas to the total body or any organ, except the thyroid, which shall be limited t less than or equal to 75 areas.
APPLICABILITY: At all times.
ACTIOWs With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of spec i fication 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, prepara and subelt to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above i
limits and includes the schedule for achieving conformance with the above !!alts. This Special Report, as defined la 10 crt Part M ' p.03['b_ll'.0S, shall include an analysis that estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the estendar year that includes the release (s) covered by this report. It shall siso describe levels of radiation and concentrations of radioactive material involved and the cause of the esposure levels or concentrations.
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142 Amendment 107 February 19,1992 l
l TS SECTION 13 l
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i 13.1.6.2 Cumuistive dose contributions from liquid and gaseous offiseste i
shall be deternised in accordsoce with Specification 13.1.4.4 sed la accordance with the methodology and parameters in the OAA
)
13.1.6.3 Cumulative dose contributions from direct radiation from the reactor units and from radweste storage tanke shall be determined in accordance with the methodology and parameters la the 000(.
This requirement is applicable only under conditions set forth la i
specification 13.1.6.1.
3 j
B ASES FOR 13.1.6.1 - TOTAL Dost This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Fart 20 by 46 ft 18525. The 1
specification requires the preparation and subalttal of a Speclat Report i
whenever the calculated doses froe plant generated radioactive effluents and
]
direct radiation exceed 25 mreas to the total body or any organ, except the j
thyroid, which shall be limited to less than or equal to 75 areas. The Special Report will describe a course of action that should result in the timitation of the annual dose to a member of the public to within the 40 CFR Part 190 lialts. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranius fuel j
cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle f acilities at the same site or within a radius et 5 mi must be considered. If the dose to any member of the public is estimated i
to exceed the requirements of 40 CFR Part 190, the special Report with a l
f -
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 C. ^L is considered to be a timely request and fulfills the requirements of 40 CF Part 190 until NRC 4
i staff action is completed. The variance only relates o the limits of 40 CFR Part 190 and does not apply in any way to the other re utrements for dose limitation of 10 CFR Part 20, as addressed in Specifications and as Individual is not considered a member of the public during any pe lod in which he/she is engaged in carrying out any operation that is part of he nuclear fuel cycle.
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143
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Amendment 107 February 19, 1992 TS SECTION 13 j