ML20073R628
| ML20073R628 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/29/1983 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20073R614 | List: |
| References | |
| NUDOCS 8305040438 | |
| Download: ML20073R628 (76) | |
Text
.. _ _.
._7_____._...._.
.\\
s
\\.' L k
.\\
s
\\.
']
ATTACHMENT I a
I
,g PROPOSED RADIOLOGIdAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS) l t}.
jg
' J 7)s
-s j,.
w i
n>
t I
'I g I' i
I,) }
s I
k\\'
l
[
s,~
s
- 3
,\\$
g f
e s
4:.
I
~ 1, s
,'s
'N 1
s s'
t.
,\\
(
1 s
e s
i 1
'+
y l
,s
,s J
i n. c 31, sy t
s s.
(.
m
\\
f 4
)
-g
~
- ),
1i s_
N i
<s t
g
\\
s,*
sx
i k,
,\\<
)
t t
,[i W
s.
g
\\_
I i, \\
g 1
k
]
f 1
/
g POWER AUTHORITY OF Tile STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
-DPR-59 8305040438 830429 PDR ADOCK 05000333 P
/
N,'s N.,
i
>.s s
i I
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS
\\
T Table of Contents b
M 1.0 Definitions 1
2.0 Liquid Effluents 3
2.1 Liquid Effluent Monitors 3
i),
a 2.2 Concentration of Liquid Effluents 5
k 2.3 Dose from Liquid Effluents 8
s, 2.4 Liquid Radioactive Waste Treatment System Operations 10 2.5 Maximum Activity in outside Tanks 12 3;
3.0 Gaseous Effluents 15 3.1 Gaseous Effluent Monitors 15 3.2 Gaseous Dose Rates 17 3.3 Air Dose, Noble Gases 21 3.4 Dose Due to Iodine-131, Iodine-133 Tritium and Radionuclides in Particulate Form 23 3.5 Main Condenser Steam Jet Air Ejector (SJAE) 25
-3.6 Offgas System 27 3.7 Offgas Treatment System Explosive Gas Mixture Instrumentation 29 4.0 Solid Radioactive Waste 33 4.1 Process Control Program 33 5.0 Total Dose 36 5.1 Total Dose from Uranium Fuel Cycle 36 6.0 Radiological Environmental Monitoring 39 6.1 Monitoring Program 39 6.2 Land Use Census Program 49 6.3 Interlaboratory Comparison Program 51 7.0 Administrative Controls 54 7.1 Responsibility 54 7.2 Procedures 54 4
3 7.3 Reporting Requirements 54 a
Amendment No.
i
RADIOLOGICAL E" FLUENT TECHNICAL SPECIFICATIONS List of Tables Table Title Page 2.2-1 Radioactive Liquid Waste Sampling and Analysis Program 6
3.2-1 Radioactive Gaseous Waste Sampling and Analysis Program 19 6.1-1 Operational Radiological Environmental Monitoring Program 42 6.1-2 Reporting Level
,e Radioactivity Concentrations in Environmental Samples 46 6.1-3 Detection Capabilities for Environmental Sample Analysis 47 Amendment No.
11
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS 5
1.0 DEFINITIONS 4
Dose Equivalent I-131 The Dose Equivalent I-131 is the concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and iso-topic mixture of I-131, 1-132, I-133, I-136 and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites" or in NRC Regulatory Guide 1.109, Revi-sion 1, October 1977.
[
Instrument Channel Calibration See Appendix A Technical Specifications.
Instrument Channel Functional Test 4
See Appendix A Technical Specifications.
Instrument Check See Appendix A Technical Specifications.
Member (s) of the Public Member (s) of the Public includes all persons who are not occupationally associated with the facilities on the PASNY/hWPC site.
This category does not include their contractors or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or - other purposes not associated with the plants, j
Offgas System The Offgas System is the system designed and installed to reduce radio-active gaseous effluents.
It collects reactor coolant system offgases and delays this release in order to reduce the total radioactivity prior to release to the environment.
Offsite Dose Calculation Manual (ODCM) f-The ODCM describes the methodology and parameters to be used in the cal-culation of offsite doses due to radioactive gaseous and liquid effluents l
and in the calculation of gasecua and liquid effluents monitoring instru-mentation alarm / trip set points.
Operable I
l See Appendix A Technical Specifications.
I i
l
[
Amendment No.
-1
The PCP is a document which identifies the current formulas, sampling methods, analyses, tests, and determinations used to control the proc-essing and packaging of solid radioactive wastes. The PCP controls these activities in such a way as to assure compliance with 10 CFR 20, 10 CFR 71 and other applicable regulatory requirements governing the disposal of the radioactive waste.
Rated Thermal Power See Rated Power, Appendix A Technical Specifications.
Site Boundary 1
The Site Boundary is that line beyond which the land is not owned, 1 cased, or otherwise controlled by PASNY and NMPC.
Refer to the ODCM for maps of the site boundary with regard to liquid and gaseous releases.
Solidification Solidification is the conversion of wet wastes into a form that meets shipping and burial ground requirements.
Source Check A Source Check is the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
Treatment Any process which effectively reduces the concentration of radioactive material per unit measure released to the environment. This includes such processes as filtration, evaporation / condensation, settling / decanting, and solidification.
Unrestricted Area An unrestricted area shall be any area at or beyond the site boundary access to which is not controlled by PASNY for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for indue-trial, commercial, institutional, and/or recreational purposes.
The definition of unrestricted area used in implementing the Radiological Effluent Technical Specifications has been expanded over that in 10 CFR
- 20. 3 (a) (17).
The unrestricted area boundary may coincide with the ex-clusion (fenced) area boundary, as defined in 10 CFR 100.3(a), but the unrestricted area does not include areas over water bodies.
The concept of unrestricted areas, established at or beyond the site boundary, is utilized in the Limiting Conditions for Operation to keep levels of ra-dioactive materials in liquid and gaseous effluents as low as is reason-ably achievable, pursuant to 10 CFR 50.36a.
Amendment No.
2
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2.0 LIQUID EFFLUENTS 2.1 LIQUID EFFLUENT MONITORS 2.1 LIQUID EFFLUENT MONITORS Applicability Applicability Applies to instrumentation required for moni-Applies to instrumentation, for monitoring ra-toring radioactive liquid effluent discharges dioactive liquid effluent discharges.
to the environment.
Objective Objective To assure that radioactive liquid effluent dis-To ensure that instrumentation required for ra-charges are properly monitored and recorded dioactive liquid effluent discharges are main-during release.
tained and calibrated.
Specifications Specifications
- a. Liquid radwaste effluent radioactivity and
- a. Operation of the radioactive liquid effluent flow rate shall be continuously monitored monitor shall be verified as follows:
and recorded during release.
If this speci-fication cannot be met, continued release of
- 1. An instrument check shall be performed liquid radwaste effluents shall be permitted prior to each release.
provided that:
- 2. An instrument channel functional test
- 1. Two independent samples of each tank are shall be performed quarterly.
analyzed; and
- 3. An instrument channel calibration shall
- 2. Twc plant personnel independently check be performed quarterly with a known ra-valving prior to discharge.
dioactive source.
NOTE: Discharge canal flow rate is based on design pump flow rates.
- b. The liquid radwaste effluent monitor shall
- b. The operability of automatic waste discharge be set to alarm and automatically close the valves and the annunciation of alarms shall waste discharge valve prior to exceeding be demonstrated prior to each release.
Amendment No.
3 A
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
the limits specified in Specification 2.2.
j The set' point for the. liquid radwaste efflu-ent monitor shall be - determined in accor-dance with methodology described in the ODCM.
With a radioactive liquid waste ef-fluent monitoring instrumentation channel alarm / trip set point less conservative than required by the ODCM:
-1. The release of radioactive liquid efflu-ents monitored by the affected channel shall be suspended; or i
- 2. The channel shall be declared inoperable; 1
or
- 3. The set point shall be changed so it is i
conservative.
j
- c. The service water system effluent pathway
- c. Operation of the service water monitor shall shall be continuously monitored for radioac-be verified as follows:
tivity during system operation.
If this specification cannot be met, operations may
- 1. An instrument check shall be performed continue provided that:
daily during system operation.
I
- 1. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples
- 2. An instrument channel functional test are collected.and analyzed for gross ra-shall be performed quarterly.
dioactivity at a Lower Limit of Detection t
i (LLD) of at least 5 x 10 7 12Ci/ml for
- 3. An instrument channel calibration shall Cs-137; and be performed quarterly with a known ra-dioactive source.
- 2. Efforts are exerted to return the instru-ment to operable status within 30 days and, if unsuccessful, an explanation is I
to be included ' in the next Semiannual Radioactive Effluent Release Report ex-j plaining why. the inoperability was not i
corrected in 30 days.
Amendment No.
4
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS t
2.2 CONCENTRATION OF LIQUID EFFLUENTS 2.2 CONPENTRATION OF LIQUID EFFLUENTS Applicability Applicability Applies to the concentration of radioactive ma-Applies to the analysis of radioactive liquid terials in liquid effluents, wastes from the plant through a liquid pathway to an unrestricted area.
l Objective Objective To ensure that the concentrations cf radioac-To ensure that analyses are performed and con-tive materials in liquid effluents are kept to centration determined for radioactive liquid acceptable levels.
releases.
Specifications Specifications
- a. The concentration of radioactive materials
- a. Radioactive liquid wastes shall be sampled released to the unrestricted areas shall and analyzed according to the sampling and not exceed the values specified in 10 CFR analyses program of Table 2.2-1.
20.106(e).
For dissolved or entrained noble gases the concentration shall be limited to 2x10 4 pCi/ml.
- b. With the concentration of radioactive mate-
- b. The results of the radioactivity analyses rial released from the plant to unrestricted shall be used in accordance with the methods areas exceeding the above limits:
in the ODCM to assure that the concentra-tions at the point of release are maintained
- 1. Restore the concentration to within the within the limits of Specification 2.2.a.
above limits; and I
i
- 2. Perform calculations to demonstrate com-1 pliance with unrestricted area radioac-i tive material concentrations specified in 10 CFR 20.106(e).
Amendment No.
5
TABLE 2.2-1 RADIOACTIVE LIQlilD WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)a Type Frequency Frequency Analysis (pci/al)
A.
Batch Waste
-6 Release Each Each Principal Gamma 5 x 10 Tanks Batch Batch Emitters"
-6 I-131 1 x 10
-5 One Bctch/M Monthly Dissolved and 1 x 10 Entrained Gases (Gamma Emitters)
-5 Each Quarterly H-3 1 x 10 d
Batch Composite Gross Alpha 1 x 10~
-8 Each Quarterly Sr-89, Sr-90 5 x 10 Batch Composite
-5 Fe-55 1 x 10 Amendment No.
6
TABLE NOTATIONS a.
The LLD is defined, for purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probabil-ity and with only 5% probability of falsely concluding that a blank ob-cervation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s b LLD
=
6 Ea V 2.22 x 10 Y + exp (-AAt) k'he re -
LLD is the a priori lower limit of detection, as defined above (in micro-curies per unit mass or volume);
s is the standard deviation of the background counting rate or of the b
counting rate of a blank sample, as appropriate (in counts per minute);
E is the counting efficiency (in counts per disintegration);
V is the sample size (in units of mass or volume);
0 2.22 x 10 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E. V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measure-ment.
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.
c.
The principal gamma emitters for which the LLD specification applies ex-clusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Cs-137.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks that are measurable and identifiable, together with the above nucliden, shall also be identified and reported in the Semiannual Radioactive Effluent Release Report.
d.
A composite sample is one in which the quantity of 1.1uid sampled is proportional to the quantity of liquid waste discharged ad in which the method of sampling employed results in a specimen that is representative of the liquids released.
Amendment No.
7
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2.3 DOSE FROM LIQUID EFFLUENTS 2.3 DOSE FROM LIQUID EFFLUENTS Applicability Applicability Applies to radiation doses from liquid efflu-Applies to the calculation of the radiation ents containing radioactive materials.
dose from liquid effluents containing radioac-tive materials.
Objective Objective To assure that the dose limitations of 10 CFR To ensure that the radiation dose from radioac-50 Appendix I for liquids are met.
tive liquid effluents is determined.
Specifications Specifications
- a. The dose to a member of the public from ra-
- a. Cumulative dose contributions from liquid dioactive materials released from the plant effluents shall be determined in accordance in liquid effluents to unrestricted areas with the ODCM at least monthly.
shall be limited as follows:
1
- 1. During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and,
- 2. During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
- b. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, the fol-lowing shall be done:
1 Amendment No.
8
-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 1. Make an investigation to identify the causes for such release rates;
- 2. Define and initiate a program of correc-tive action; and
- 3. In lieu of a Licensee Event Report, prepare and submit a report to the NRC within 30 daya from the end of the quar-ter during which such releases occurred.
l Amendment No.
9 l
~~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4
i d,
1 2.4 LIQUID' RADIOACTIVE ' WASTE TREATMENT SYSTEM 2.4 LIQUID RADIOACTIVE WASTE TREATMENT SYSTEM OPER-OPERATIONS ATIONS Applicability Applicability Applies to the operability of radioactive lig-Dose projections apply to liquid effluents re-uid processing equipment, leased to unrestricted areas.
I Objective Obj ect tve To ensure liquid radwaste treatment system (s)
To ensure that action levels to require opera-are operated to prevent exceeding the dose lim-tion of waste treatment systems are determined.
its of Specification 2.3.
Specifications Specifications,
- a. The liquid radioactive waste treatment sys-
- a. Doses to individuals in unrestricted areas I
tem shall be used when the projected dose due to liquid releases shall be projected at from untreated liquid releases, over a 31 least monthly in accordance with ODCM.
day period, to a member of the public would exceed:
2-
- 1. 0.06 mrem to t'r.e whole body; or,
- 2. 0.2 mrem to any organ.
- b. With radioactive liquid waste being dis-charged in excess of the above limits, in j
lieu of a Licensee Event Report, prepare l
and submit to the Commission within 30 days a report that includes the following infor-i mation:
i
- 1. Explanation if liquid radwaste was being J
discharged without treatment; and if so:
i Amendment No.
10 4
t LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 2. Identification of any inoperable equip-ment or subsystems and the reason for the inoperability;
- 3. Action (s) taken to restore the inoperable equipment to operable status; and
- 4. Summary description of action (s) taken to prevent a recurrence.
Amendment No.
11
i
}
LIMITING CONDITIONS FOR OPERATION.
SURVEILLANCE REQUIREMENTS-l 2.5 MAXIMUM ACTIVITY IN OUTSIDE TANKS 2.5 MAXIMUM ACTIVITY IN OUTSIDE TANKS Applicability Applicability Applies to tanks located outdoors.
Applies to outdoor tanks.
Objective.
Objective To ensure that in the event of an uncontrolled To ensure that the radioactivity contained in release of the tank's contents, the resulting outdoor tanks is kept within applicable limits.
concentrations would be less than the limits of 10 CFR 20, Appendix B. Table II, Column 2, f
at the nearest surface water supply in an un-1 restricted area.
Specifications Specifications
- a. The quantity of liquid radioactive material
- a. The quantity of radioactive material con-contained in a condensate storage tank or tained in a condensate. storage tank or any j
any outside temporary tank shall be limited outside temporary tank shall be determined 4
to 10 curies, excluding Tritium and dis-by analyzing a liquid sample of the tank's solved or entrained noble gases.
contents weekly when radioactive liquid is
- b. With the quantity of liquid radioactive ma-I terial in a tank above this limit, reduce the tank's radioactive contents to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; and
- c. In lieu of a Licensee Event Report, describe the events leading to this condition in the next Semiannual Effluent Release Report.
l I
Amendment No.
12 1
e
9 BASES 2.0 LIQUID EFFLUENTS 2.1 LIQUID EFFLUENT MONITORS The radioactive liquid effluent instrumentation is provided to monitor and control the releases of radioactive materials in liquid effluents during planned or unplanned releases.
The alarm / trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the lim-its of 10 CFR 20.
The operability and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60, 63 and 64 2.2 CONCENTRATION OF LIQUID EFFLUENTS This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents to unrestricted areas will be less than the concentration levels specified in 10 CFR 20, Appen-dix B. Table II, Column 2.
.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposure above (1) the design objectives of 10 CFR 50, Appendix I, Section II.A. to a member of the public and (2) the limits of 10 CFR 20.106(e) to the population.
The concentration limit for dissolved or entrained noble gases is based on Xe-135 as the control-ling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described -in ICRP Publication 2.
' 2.3 DOSE FROM LIQUID EFFLUENTS This specification is provided to assure that the requirements of 10 CFR 50, Appendix I, Section II.A. III.A and IV.A are met.
The Limiting Con-ditions for Operation assures that the guides set forth in Appendix I,Section II.A are met.
The specifications provide the required operating flexibility and, at the same time, implement the guides set forth in Appendix I,
Section. IV. A.
to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."
2.4 LIQUID RADIOACTIVE WASTE TREATMENT SYSTEM OPERATIONS The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".
This specification assures that the requirements of 10 CFR 50.36a, 10 CFR 50, Appendix A, General Design Criterion 60, and design objective of 10 CFR 50, Appendix I, Section II.D are met.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in 10 CFR 50, Appendix I, Section II.A. for liquid effluents.
Amendment No.
13
BASES 2.5 MAXIMUM ACTIVITY IN OUTSIDE TANKS Restricting the quantity of radioactive material contained in the speci-fied tanks provides assurance that, in the event of an uncontrolled re-lease of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B.
Table II, Column 2, at the nearest drinking water supply currently in use and at the nearest surface water supply in an unrestricted area.
i i
l l
l Amendment No.
14 1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.0 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS 3.1 GASEOUS EFFLUENT HONITORS Applicability Applicability These requirements apply to instruments which Applies to instrumentation listed in Specifi-monitor the gaseous radioactivity effluent cation 3.1.a and analyses of gaseous effluent pathways to the environment, releases.
Objective Objective To assure that radioactive gaseous effluent To ensure that instrumentacion required for discharges are properly monitored and recorded gaseous effluent releases is maintained and during release.
calibrated and the radioactivity of gaseous re-leases is determined.
Specifications Specifications
- a. Radioactive gaseous wastes released to the
- a. Operation of the gaseous effluent monitors environment via the below listed pathways listed in Specification 3.1.a shall be veri-shall be monitored and recorded during re-fied as follows:
lease from the respective pathway.
- 1. An instrument check shall be performed
- 1. Main stack daily during release from each respective pathway.
- 2. Refuel floor vent
- 2. An instrument channel functional test and
- 3. Reactor building vent a source check shall be performed quar-terly.
- 4. Turbine building vent
- 3. An instrument channel calibration shall
- 5. Radwaste building vent be performed quarterly with a known ra-dioactive source.
Amendment No.
15 a
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- b. Each pathway listed in a.
above, shall also
- b. The iodine cartridge and the particulate be sampled for iodine and particulate radio-filter for each pathway listed in Specifi-activity on a continuous basis during re-cation 3.1.a shall be changed out at least lease from the respective pathway.
weekly.
- c. If Specifications 3.1.a and b.,
above, can-
- c. Grab samples, when required, shall be col-not be met, effluent releases may continue lected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and ana-via the respective pathway provided gaseous lyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of collection. Auxil-grab samples are collected in the case of a inry samplers shall run continuously and be monitor out of service and auxiliary sam-changed out at least weekly.
plers are used in case a particulate or io-dine sampler is out of service;
- 1. Return the instrument to operable status within 30 days; or
- 2. Provide an explanation in the next Semi-annual Radioactive Release Report as to why the inoperability was not corrected within 30 days,
- d. Alarm / trip set points shall be determined in accordance with the ODCM and set to ensure that the limits of Specification 3.2 are not exceeded.
With a radioactive gaseous ef-fluent monitoring instrumentation channel alarm / trip set point less conservative than required by the above specification:
- 1. Suspend the release of radioactive gas-eous effluents monitored by the affected channel; or
- 2. Declare the channel inoperable; or
- 3. Change the set point so it is acceptably conservative.
Amendment No.
16
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REQUIREMENTS 3.2 GASEOUS DOSE RATES 3.2 CASEOUS DOSE RATES Applicability Applicability Applies to the radiation dose from radioactive Applies to the calculation of the dose rates material in gaseous effluents from the plant, from radioactive naterials in gaseous effluents 4
from the plant.
Objective Objective To ensure that the dose rates at or beyond the To ensure that appropriate calculations are site boundary from gaseous effluents do not performed to determine the dose rates from exceed the annual dose limits of 10 CFR 20 for gaseous effluents from the plant.
unrestricted areas.
Specifications Specifications
- a. The annual dose rate at or beyond the site
- a. The dose rate due to noble gases in gaseous boundary due to radioactive materials re-effluents shall be determined to be contin -
leased from the plant in gaseous effluents uously within the limits of Specification shall be limited as follows:
3.2.a.
in accordance with the methods and procedures of the ODCM.
- 1. 5500 mrem to the whole body and $3000 mrem to the skin from noble gases; and,
- 2. 51500 mrem to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days.
- b. With the dose rate (s) exceeding the above
- b. The dose rate due to Iodine-131, Iodine-133, limits, restore the release rate to within Tritium and to radionuclides in particulate the above limits.
form with half-lives greater than 8 days in Amendment No.
17
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM. This will be done by obtaining representative samples and performing analyses in accor-dance with the sampling and analyses program specified in Table 3.2-1.
1 I
I l
1 j
1 Amendment No.
18
[
TABLE 3.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRMi Lower Limit Minimum of Detection Gaseous Release Sampling Analysis Type of Activity (LLD)a Type Frequency Frequency Analysis (pCifnl)
~4 Mai's Stack and Monthly Monthly Noble Gas 1 x 10 Refuel Floor Vent Grab Emitters and Sample Reactor Building Vent and Quarterly Quarterly H-3 1 x 10'E Turbine Building Grab Sample Vent and
-12 Radwaste Building Continuous" Weekly 1-131 1 x 10 Vent Charcoal Sample
~II Continuous" Weekly Principal Gamma 1 x 10 Particulate Emitters Sample (I-131, others) e
-1 Continuous 1 Wk/Mo Gross Alpha 1 x 10 Particulate Sample
-11 Continuous" 4 Wk/Qr Sr-89, Sr-90 1 x 10 Composite Particulate Sample
-5 Continuous" Noble Gas Noble Gases 1 x 10 Monitor Gross Beta or Gamma
(
Amendment No.
19
~.
TABLE NOTATIONS a.
The LLD is defined, for purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probabil-icy and with only 5% probability of falsely concluding that a blank ob-servation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD
=
Ea Va 2.22 x 106, 7,,xp (_33t)
Where:
LLD is the a priori lower limit of detection, as defined above (in micro-curies per unit mass or volume);
s is the standard deviation of the background counting rate or of the b
counting rate of a blank sample, as appropriate (in counts per minute);
E is the counting efficiency (in counts per disintegration);
V is the sample size (in units of mass or volume);
0 2.22 x 10 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
b.
The principal gamma emitters for which the LLD specification applies ex-clusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous emissions; and, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Cs-137 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported, c.
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 calcula-tion made in accordance with Specifications. This determination shall be made using design flow rates if flow meters are not provided or are inoperable.
Amendment No.
20
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 AIR DOSE, NOBLE CASES 3.3 AIR DOSE, NOBLE GASES Applicability Applicability Applies to the air dose due to noble gases re-Applies to the calculation of the air dose due leased from the plant.
to noble gas effluent.
Objective Objective To assure that the noble gas dose limitations To ensure that appropriate calculations are of 10 CFR 50, Appendix I, are met, performed to determine the air dose from noble gas effluents.
Specifications Specifications
- a. The air dose to areas at or beyond the site
- a. Curilative air dose contributions for noble boundary from noble gases released from the gases shall be calculated at least monthly plant in gaseous effluents shall be limited:
in accordance with the ODCM.
- 1. During any calendar quarter, to less than or equal to 5 mrad f rom gamma radiation, and less than or equal to 10 mrad from beta radiation; and,
- 2. During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.
- b. With the calculated air dose from radioac-tive noble gases in gaseous effluents ex-ceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission, within 30 days, a report that:
Amendment No.
21
LIMITING CONDITIONS-FOR OPERATION SURVEILLANCE REQUIREMENTS
- 1. Identifies the cause(s) for exceeding the limit (s); and
- 2. Defines the corrective actions that have been taken to reduce the releases; and
- 3. Identifies the proposed corrective ac-tions to be taken to assure than subse-quent releases will be in compliance with the above limits.
Amendment No.
22
r LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 DOSE DUE TO 10 DINE-131, 10 DINE-133, TRITIUM AND 3.4 DOSE DUE TO IODINE-13), IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM RADIONUCLIDES IN PARTICULATE FORM Applicability Applicability Applies to the cumulative dose from Iodine-131, Applies to the calculation of the dose due to Iodine-133, Tritium, and radionuclides in par-Iodine-131, Iodine-133, Tritium, and radionu-ticulate form in gaseous effluents.
clides in particulate form in gaseous efflu-ents.
Objective Obj ective To assure that the dose limitations of 10 CFR To ensure that appropriate calculations are 50, Appendix I, are met.
performed to determine the dose from Io-dine-131, Iodine-133, Tritium, and radionu-clides in particulate form.
Specifications Specifications
- a. The dose to a member of the public at or
- a. Cumulative dose contributions shall be cal-beyond the site boundary from Iodine-131, culated at least monthly in accordance with Iodine-133, Tritium, and radionuclides in the ODCM.
particulate form with half-lives greater than 8 days released from the plant in.
gaseous effluents shall be limited:
- 1. During any calendar quarter to less than or equal to 7.5 mrem to any organ; and,
- 2. During any calendar year to less than or equal to 15 mrem to any organ.
- b. With the calculated dose from the release of Iodine-131, Iodine-133, Tritium, and radio-nuclides in particulate form with half-lives greater than 8 days, in gaseous effluents i
{
Amendment No.
23
-e
' _ /f i'
- f,.
j
,. (,
.).
j' f'
s a
r',
_, " ri Q
LIMIT!hG CONDITIONS FOR OPERATION
, SURNEILLAN';E REQUIREMENTS o
l exceeding any of the above limits, in lieu of a Licensee Ev er.t Report, prepare and submit to the Commisrion within 30 days a report that:
- 1. Identifies the cause(s) for exceeding the limit; and
- 2. Defines the corrective actions that have been taken to reduce the releases; and
- 3. Identifies the ' proposed corrective ac-tions to be taken to' assure that subse-
.j y
/ quent releases will be in compliance with the above limits.
4 l<
~., _,
s e
y
'r
. ~
/
/
,~
.J su
/
e 4
r a
4
~..
'f i
's Amendment No.
24
.s.
s Y
,,. ~
W i
1 LIMITING CONDITIONS I'OR OPERATION SWlVflLLANCE REQUIREMENTS
~
t 3.5 MAIN CONDENSER STEAM JET AIR EJECTOR (SJAE)[
3.5 MAIN CONDENSER STEAM JET AIR VJECTOR (SJAE)
Applicability Applicabf M y, _
_i
/
g a.
Applie-tomaincondenseroffgasdischargs-[ ate'.
Appl 14s t3.the' point of fdischargf at the SJAE.
for noble gases.
e j
J Objective f;
Obj ective l
e To ensure that the SJAE release rates are main-To, ensure that the SJAE release rates are prop-tainell at a level compatible for further treat-erly. monitored.
pent and release.
~
Specifications Specifications
- a. The gross radioactivity (beta and/or gamma)
- a. The gross radioactivity (beta and/or gamma) rate of noble gases measured at the SJAE rate of noble gases from the SJAE shall be shall be limited to less then, 500,000 determined to be within the limits of'Speci-pCi/sec.
/
'fication 3.5.a by~ performing an isotopic
[
,/ analysis of a representative sample of gases
- 1. With the gross radioactivity exec: ding
' taken at the dischstge (prior to dilution the above limit, bring the SJAE release and/or discharge) of the SJAE ai follows:
rate within the above limit _ within 72
- 1. At leasF monthly.'
hours or be in at least hot standby with-in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
~'
~
r
- 2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following ca increase as indicated by the SJAE Monit-)r, of greater than 50% (after factoring out increases j
due to changes in thermal power Jevel) in the nominal steady state fission gas re-lease from the primary coolant.
Amendment No.
25
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- b. Except as specified in 1. below, both SJAE
- b. Operation of the SJAE radioactive offgas system radiation monitors shall be operable monitors r. hall be verified as follows:
during reactor. power operation.
The trip time delay setting for closure of the SJAE
- 1. An instrument check shall be performed isolation valve shall not exceed 15 min.
daily during release from each respective pathway.
- 1. In the event that one of the two SJAE radiation monitors is made or found to
- 2. An instrument channel calibration shall be inoperable, continued reactor power be performed quarterly.
operation is permissible provided that the inoperable monitor is tripped in the
- 3. An instrument channel functional test downscale position.
shall be performed semiannually.
- 2. Upon the loss of both SJAE system radia-tion monitors, either temporary monitors shall be used to monitor radiation re-leases to the environs, or initiate an orderly shutdown and have the main steam isolation valves closed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Amendment No.
26
4 LIMITING. CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 0FFGAS SYSTEM 3.6 0FFCAS SYSTEM Applicability Applicability Applies to the system installed for reduction Applies to the calculation of the radiation of radioactive materials in gaseous waste prior dose from gaseous effluents containing radioac-to discharge.
tive materials.
Objective Objective To minimize concentration of radioactive mate-To ensure that treatment of gaseous wastes by rials released from the site.
the offgas system is implemented when required.
Specifications Specifications 1
- a. The offgas treatment system shall be used
- a. Doses due to gaseous releases from.the site to reduce the concentration of radioactive shall be proj ected at least monthly in ac-materials in gaseous effluents prior to cordance with the ODCM.
release from the plant, when the projected air dose, over d 31 day period, to areas at and beyond the site boundary, would exceed:
- 1. 0.2 mrad for gamma radiation; or,
- 2. 0.4 mrad for beta radiaticn; or,
- 3. 0.3 mrem to any organ,
- b. With gaseous waste _being discharged in ex-cess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a report that includes the following information:
Amendment No.
27
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 1. Identification of the causes, including any inoperable equipment or subsystems, and the reason for their inoperability;
- 2. Action (s) taken to restore release to within the above limits and/or restore any inoperable equipment to operable status; and
- 3. Summary description of action (s) taken to prevent a recurrence.
J l
Amendment No.
28
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 0FFGAS TREATMENT SYSTEM EXPLOSIVE CAS MIXTURE 3.7 0FFGAS TREATMENT SYSTEM EXPLOSIVE CAS MIXTURE INSTRUMENTATION INSTRUMENTATION Applicability Applicability Applies to the condenser offgas treatment sys-Applies to the offgas treatment system instru-tem reconbiner operation.
mentation, which monitors the critical oper-ating parameters of the primary recombiner.
Objective Objective To ensure proper conditions for the offgas re-To ensure that instrumentation required for au-ccmbiner to operate at design efficiency ir.
tomatic isolation is maintained and calibrated.
order to prevent an explosive mixture of gases in the charcoal treatment system.
Specifications Specifications
- a. The following instrumentation shall be.oper-
- a. Operation of the explosive gas mixture in-ational and capable of providing automatic struments listed in Specification 3.7.a isolation of the offgas treatment system shall be verified, under the following conditions:
- 1. An instrument check shall be performed
- 1. The offgas dilution steam flow instrumen-daily when the offgas treatment system is tation shall alarm and automatically iso-in operation.
late the offgas treatment system at low flow less than 6000 pounds per hour or
- 2. An instrument channel functional test high flow greater than 7200 pounds per shall be performed once per operating hour.
cycle.
- 2. The offgas inlet temperature sensor shall
- 3. An instrument channel calibration shall alarm and automatically isolate the off-be performed once per operating cycle, gas treatment system at a temperature less than 125"C.
Amendment No.
29
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 3. The primary offgas recombiner outlet tem-perature shall alarm and automatically isolate the offgas treatment system on a temperature less than 150*C.
- b. The concentration of hydrogen in the con-
- b. With condenser offgas treatment system re-denser offgas treatment system recombiner combiner in service, the hydrogen content discharge shall be limited to less than or shall be verified weekly to be 54% by volume, equal to 4% by volume.
- c. With the requirements of the above specifi-cations not satisfied, restore the system to within operating specifications or suspend use within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
1 Amendment No.
30
BASES 3.0 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS The radioactive gaseous effluent instrumentatien is provided to monitor and control the releases of radioactive materials in gaseous effluents during planned or unplanned releases.
The alarm / trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the lim-its of 10 CFR 20.
The operability and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60, 63 and 64.
3.2 GASEOUS DOSE RATES This specification is provided to ensure that the dose at or beyond the site boundary from gaseous effluents will be within the annual dose lim-its of 10 CFR 20.
The annual dose limits are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharges in gaseous effluents will not result in the exposure of a member of the public to annual average concentrations exceeding the limits specified in 10 CFR 20, Appendix B. Table II (10 CFR 20.106[b]).
The specified limits restrict, at all times, corresponding gamma and beta dose above back-ground to an individual at or beyond the exclusion area boundary to 5500 mrem / year to the total body or to 53000 mrem / year to the skin. These lim-its also restrict the corresponding thyroid dose above background to an infant via the cow-milk-infant pathway to $1500 mrem / year for the cow nearest to the plant.
3.3 AIR DOSE, NOBLE GASES This specification is provided to assure that the requirements of 10 CFR 50, Appendix I, Section II.B. III.A and IV.A are met.
The Limiting Con-ditions for Operation are the guides set forth in Appendix I,Section II.B.
The specification provides the required operating flexibility and, at the same time, implements the guides set forth in Appendix I,Section IV.A, to assure that the releases of radioactive material in gaseous ef-fluents will be kept "as low as is reasonably achievable."
3.4 DOSE DUE TO 10 DINE-131, 10 DINE-133, TRITIUM AND RADIONUCLIDES IN PARTIC-ULATE FORM This specification is provided to assure that the requirements of 10 CFR 50, Appendix I, Section II.C. III.A and IV.A are met.
The Limiting Con-ditions for Operation are the guides set forth in Appendix I,
Section II.C.
The specifications provide the required operating flexibility and, Amendment No.
31
BASES at the same time, implement the guides set forth in Appendix I,Section IV.A. to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."
3.5 MAIN CONDENSER STEAM JET AIR EJECTOR (SJAE)
This specification is provided to assure that remedial action is tcken to limit the noble gas release rate at the SJAE.
The requirement provides reasonable assurance that the amount of noble gas 'that must be treated and/or released is controlled to a level that prevents exceeding the lim-its specified in 10 CFR 20, Appendix B, Table'll.
3.6 0FFGAS SYSTEM This specification is provided to ensure that the system will be avail-able for use when required to reduca projected quarterly and annual doses due to gaseous releases.
This specification assures that the require-ments of 10 CFR 50.36a, 10 CFR 50, Appendix A, General Design Criterion 60, and design objective in 10 CFR 50, Appendix I, Section II.D are met.
The specified limits governing the uce of ~ appropriate portions of the systems are specified as a suitable fraction of the guide values set forth in 10 CFR 50, Appendix I, Sections II.B and II.C. for gaseous ef-fluents.
3.7 0FFGAS TREATMENT SYSTEM EXPLOSIVE GAS MIXTURE INSTRUMENTATION This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in portions of the offgas treat-ment system not designed to_ withstand a hydrogen-explosion is maintained
-below the lower explosive limit of hydrogen. The proper operation of the primary recombiner ensures - that the charcoal contained in the condenser offgas treatment system is not exposed to an explosive mixture of gases.
Thus it provides assurance that. the releases of radioactive materials will be controlled in conformance with the requirements of 10 CFR 50, Appendix A,-General Design Criterion 60.
Amendment No.
32
i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.0 SOLID RADIOACTIVE WASTE 4.1 PROCESS CONTROL PROGRAM 4.1 PROCESS CONTROL PROGRAM Applicability Applicability Applies to radioactive solid waste packages for Applies to the solidification system utilized offsite shipment, for wet solid wastes.
Objective Objective To ensure that the applicable requirements of To ensure that solidification of wet solid 10 CFR 20 and 10 CFR 71 are met prior to ship-wastes is performed in accordance with the PCP.
ment.
Specifications Specifications
- a. The solid radwaste system shall be used in
- a. The PCP shall be used to verify the solidi-accordance with the PCP to process wet ra-fication of at least one representative test dioactive wastes to meet shipping and burial specimen from at least every tenth batch of ground requirements.
each type of wet radioactive waste.
- 1. If any test specimen fails to verify so-lidification, the solidification of the batch under test shall be suspended until the following are completed:
a) Additional test specimens can be ob-talned; b) Alternative solidification parameters can be determined in accordance with the PCP; and Amendment No.
33
~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS c) A subsequent test verifies solidifi-cation.
Solidification of the batch may then be resumed using the parameters determined by the PCP.
- 2. If the initial. test specimen from a batch of waste fails to verify solidification, the PCP' shall provide for the. collection and testing of representative test speci-mens from each consecutive batch of the same. type'of wet waste until at least 3 consecutive initial test specimens. demon-strate solidification.
The PCP shall be modified as required, to assure solidifi-cation _of subsequent batches of waste,
- b. With the provisions of the' PCP not satis-fled, suspend shipments of affected packaged solid ~;adioactive wastes from-the site.
Amendment No.
34
)
I' BASES 4.0. SOLID RADIOACTIVE WASTE This specification assures that. the requirements of 10 CFR 50.36a and 10 CFR 50, Appendix A, General Design Criterion 60 are met.
The process parameters included in establishing a PCP may include, but.are not 112-ited to:
waste type, waste pH,- waste / liquid / solidification / agent /ca-talyst ratios, waste oil content,' waste principal chemical constituents, mixing and curing times.
1 4
t 4
4 4
i 1
s i
i -
l 1
4 f
Amendment No.
35 i
I
-...m
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 5.0 TOTAL DOSE 5.1 TOTAL DOSE FROM URANIUM FUEL CYCLE 5.1 TOTAL DOSE FROM URANIUM FUEL CYCLE Applicability Applicability Applies to radiation dose from releases of ra-Applies to the calculation of total dose due to dioactivity and radiation from uranium fuel releases of radioactivity and radiation from cycle sources.
uranium fuel cycle sources.
Objective Objective To assure that the requirements of 40 CFR 190 To ensure that appropriate calculations are are met.
performed to determine total dose to a member of the public.
Specifications Specifications
- a. The annual (calendar year) dose or dose com-
- a. Dose Calculations Cumulative dose contribu-mitment to any member of the public, due to tions from liquid and gaseous effluents releases of radioactivity and radiation, shall be determined in accordance with Spec-from uranium fuel cycle sources shall be ifications 2.3.a, 3.3.a.
and 3.4.a and in limited as follows:
accordance with the ODCM.
- 1. Less than or equal to 25 mrem to the whole body; and,
- 2. Less than or equal to 25 mrem to any or-gan except the thyroid which shall be limited to less than or equal to 75 mrem.
- b. With the calculated doses from the release of radioactive materials in liquid or gas-eous effluents exceeding twice the limits Amendment No.
36
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS of Specification 2.3.a or 3.3.a or 3.4.a, calculations shall be made to determine whether the limits of 5.1 have been ex-ceeded.
If this is the case, in lieu of a Licensee Event Report: a report defining corrective actions to be taken to reduce subsequent releases to levels within limits, along with a schedule for achieving confor-mance, shall be prepared and submitted to the Commission within 30 days. This report, as defined in 10 CFR 20.405c, shall include estimates of the radiation exposure (dose) to a member of the public from uranium fuel cycle sources, including all effluent path-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 concentration of radioac-tive material involved, and the cause of the exposure levels or concentrations.
If the estinated dose (s) exceed (s) the above lim-its, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the report shall include a request for variance in accordance with the provisions of 40 CFR 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
Amendment No.
37
BASES 5.0 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190.
This specification requires the preparation and cubmittal of a re-port whenever the calculated dose from plant radioactive effluents exceed twice the design objective doses of 10 CFR 50, Appendix I.
The 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 190 lim-its.
For the purpose of the report, it may be assumed the dose commit-ment to the member of the public from other uranium fuel cycle sources is negligible.
However, dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be con-sidered.
If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the report, with a request for variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), shall be submitted in accordance with provisions of 40 CFR 190.11 and 10 CFR 20.405c.
This request is con-sidered a timely requeet and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the requirements for dose limitation addressed in Specifications 2.0 and 3.0.
An individ-ual 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 nu-clear fuel cycle.
Amendment No.
38
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.1 MONITORING PROGRAM 6.1 MONITORING PROGRAM Applicability The radiological environmental' monitoring sam-ples shall be collected, pursuant to Table At all times.
6.1-1, from the locations given in the table and figure (s) in the ODCM and shall be analyzed Objective pursuant to the requirements of Table 6.1-1, and the detection capabilities required by To evaluate the effects of plant operation on Table 6.1-3.
the environs and to verify the effectiveness of the controls on radioactive material.
Specifications
- a. With the radiological environmental moni-toring program not being conducted as speci-fled in Table 6.1-1, in lieu of a Licensee Event Report prepare and submit to the Com-mission, in the Annual Radiological Environ-mental Operating Report, a description of-the reasons for not conducting the program as required and the plans for preventing a recurrence.
(Deviations are permitted from the required sampling schedule if samples are unobtain-able due to hazardous conditions, seasonal unavailability, theft, uncooperative resi-dents, or to malfunction of automatic sam-pling equipment.
If the latter, efforts shall be made to complete corrective action prior to the end of the next sampling period.)
Amendment No.
39
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- b. With the level of radioactivity (as the re-sult of plant effluents) in an environmental sampling medium exceeding the reporting lev-els of Table 6.1-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Com-mission within thirty (30) days from the end' of the affected calendar quarter a report.
This report shall identify the cause(s) for exceeding the limit (s) and define the cor-rective action (s) to be taken to reduce ra-dioactive effluents so that the calculated annual dose to a member of the' public is less than the calendar year limits of Speci-fications 2.3, 3.3, and 3.4.
Wl'en mote than one of the radionuclides in Table 6.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1), concentration (2) + * * *
- 2:1* 0 limit level (1) limit level (2)
When radionuclidee other than those in N-ble 6.1-2 are detected and are the result of plant effluents, this report shall be sub-mitted if the calculated annual dose to an individual is equal to or greater than the calendar year limits of Specification 2.3, 3.3, and 3.4.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and de-scribed in the Annual Radiological Environ-mental Operating Report.
Amendment No.
40
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6.1-1, locations for obtaining replacement samples shall be identified and added to the radiological environmental nonitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted f rom the monitoring program.
In_ lieu of a Licensee Event Report, the cause of the un-availability of samples and the new loca-tion (s) for obtaining replacement samples shall be identified in the next Semiannual Radioactive Effluent Release Report.
Also included in the report shall be a revised figure (s) and table fer the ODCM reflecting the new location (s).
1 Amendment No.
41 k
TABLE 6.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGFJW Exposure Sampling and and/or Sample Number of Samples a) and Locations Collectiog)
Type and Frequency Pathway Frequency of Analysis AIRBORNE Radioiodine Samples from 5 locations:
Continuous sam-Radiciodine Canisters:
and ple operation Analyze weekly for I-131.
Particulates a.
3 samples from offsite locations in dif-with sample col-ferent sectors of the highest calculated lection weekly Particulate Samples:
site average D/Q (based on all licensed or as required Grossbetaradioactivit{b) site reactors).
by dust loading, following filter change whichever is composite (bylocayign) b.
1 sample from the vicinity of a community more frequent.
for gamma isotopic having the highest calculated site aver-quarterly (as a minimum).
age D/Q (based on all licensed site re-actors).
c.
I sample from a control location 9 to 20 milesdistantggjintheleastprevalent wind direction Direct 32 stations with two or more dosimeters Quarterly Gamma dose monthly or Radiation (
plcced as follows: An inner ring of stations quarterly.
in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors of each ring. There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residencies, schools, and in 2 or 3 areas to serve as control stations.
Amendment No.
42
TABLE 6.1-1 (continued)
Exposure Sampling and Pathway and/or Sample Number of Samples (a) and Locations Collectiog Type and Frequency Frequency of Analysis WATERBORNE Surface ( }
a.
1 sample upstream.
Composite sam-Gamma isotopic analysis ple over one monthly composite for b.
I sample from the site's most downstream month period (g)
Tritium analysis quar-cooling water intake.
terly.
Sediment from I sample from a downstream area with existing Twice per year.
Gamma isotopic analysis Shoreline or potential recreational value.
semiannually.
Discharge a.
I sample from the discharge canal.
Composite sam-Gamma isotopic analysis Capel ple over one quarterly.
month period (8 INCESTION Milk a.
Samples from milch animals in 3 locations Twice per month, Gamma isotopic and I-131 within 3.5 miles distant having the high-April through analysis twice per month est calculated site average D/Q.
If December (sam-when milch animals are there are none, then 1 sample from milch ples will be on pasture (April through animals in each of 3 areas 3.5 to 5.0 collected in December); monthly (Jan-miles distant having the highest calcu-January through uary through March), if lated site average D/Q (based on all March if I-131 required.
licensed site reactors),
is detected in November and b.
I sample from milch animals at a control December of the location (9to20milesdistan[dindina preceding year).
less prevalent wind direction)
Amendment No.
43
TABLE 6.1-1 (continued)
Exposure Sampling and Pathway and/or Sample Number of Samples,) and Locations Collectioy,)
Type and Frequency Frequency of Analysis Fish a.
I sample of each of 2 commercially or Twice per year.
Gamma isotopic analysis recreationally important species in the of edible portions.
vicinity of a site discharge point.
b.
I sample of each of 2 species (same as in a. above or of a species with similar feedinghabits)fromanarcid9tleast5 miles distant from the site Food Producta a.
3 samples of broad leaf vegetation grown Monthly when Gamma isotopic analysis.
at the nearest offsite locations of high-available est calculated site average D/Q if milk sampling is not performed (based on all licensed site reactors).
b.
In lieu of a garden census as specified Once, during Gamma isotopic analysis, in 6.2, 3 samples of broad leaf vegeta-harvest season.
(Isotopic to include bles shall be collected from available I-131.)
offrite locations of highest calculated site average D/Q for elevated release points.
In addition, 3 samples will be collected from available offsite loca-tions of highest calculated site average D/Q for ground level release points (based on all licensed site reactors).
c.
1 sample of each of similar broad leaf Once, during Gamma isotopic analysis.
in harvest season.
(Isotopic to include vegetationgrown9to20milesjgytant a less prevalent wind direction I-131.)
Amendment No.
44
TABLE NOTATIONS (a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report.
Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the ODCW) for all licensed site reactors.
(b) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity in air is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(c) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant.
(d) The purpose of these samples is to obtain background information.
If it is not practical to establish centrol locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addi-tion to, integrating dosimeters.
For the purpose of this table, a thermo-luminescent dosimeter may be considered to be one phosphor and two or more-phosphors in a pocket may be considered as two or more dosimeters.
Film badges shall not be used for measuring direct radiation.
(f) The " upstream sample" shall be taken at a distance beyond significant in-fluence of the discharge.
The " downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.
(g)- Composite samples should be collected with equipment (or equivalent) which
{
is capable of collecting an aliquoit at time inte rvals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure that a representative sample is obtained.
(h) Reporting Levels for Radioactivity Concentrations in Environmental Samples (Table 6.1-2) are not applicable to discharge canal samples.
Amendment No.
45
TABLE 6.1-2 REPORTING LEVEL FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAHPLES REPORTING LEVELS Water Airborne Particulate Fish Milk Food Products 3
Analysis (pCi/1) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr/Nb-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 l
Ba/La-140 200 300 Amendment No.
46
DETECTION CAPABILITIES FOR E IRblaENTALSAM LOWER LIMIT OF DETECTION (LLD) g ANALYSIS Water Airborne Particulate Fish Milk Food Products Sediment 3
Analysis (pCi/1) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg, dry) gross beta 4
0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr/Nb-95 15 I-131 1( }
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 Amendment No.
47 i
m TABLE 6.1-3 (continued)
TABLE NOTATIONS (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical sep-aration),
4.66 sb
" E V
2.22 Y
exp (- Aat)
Where:
LLD is the a priori lower limit of detection, as defined above (in pico-curie per unit mass or volume);
s is the standard deviation of the background counting rate or of the b
counting rate of a blank sample, as appropriate (in counts per minute);
E is the counting efficiency (in counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide:
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
Typical values of E, V, Y, and At should be used in the calculations.
(b) It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measure-ment.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluc-tuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identi-fied and described in the Annual Radiological Environmental Operating Report.
(c) LLD for drinking water samples.
If no drinking water pathway exists, the LLD of the gamma isotopic analysis may be used.
Amendment No.
48 L
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 6.2 LAND USE CENSUS PROGRAM
- 6. 2 ' LAND USE CENSUS PROGRAM Applicability The land use census shall be conducted during the growing season at least once per 12 months At all times.
using the information that will provide the best results, such as by a door to door survey, Objective aerial survey, or by consulting local agricul-ture authorities, etc.
The results of the land To identify locations of milch animals and gar-use census shall be included in the Annual-Ra-dens of greater than 50 square meters within 3 diological Environmental Operating Report, miles of the site.
Specifications
- a. A land use census shall be. conducted and shall identify the locations of all milch animals, the nearest. residence, and all gar-dens
- of greater than 50 square meters pro-ducing fresh leafy vegetables, in each of the 16 meteorological sectors within a dis-tance of 5 miles from the site.
- b. With a land use. census identifying a milch animal in a location (s) which represents a calculated D/Q value greater than time values currently being used in calculating Surveil-lance Requirement 3.4, in lieu of a Licensee Event Report, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report.
Broad leaf vegetation sampling may be performed in lieu of the garden census as specified in Table 6.1-1.
Amendment No.
49
f, I
LIMITING CONDITIONS FOR' OPERATION' SURVEILLANCE REQUIREMENTS
- c. With the. land use census identifying a milch animal location (s)' that represents a calcu-lated D/Q. (via. the same ' exposure pathway)'
significantly greater. (5 times) than at a.
location from which samples. are currently b'eing.obtained 'in accordance with Table:
6.1-1, add the new location (s) to'the radi-i ological environmental monitoring-~ program within 30 days.
The sampling location (s),
excluding. the = control station ~ location, i
having the lowest calculated D/Q l(via the same exposure pathway) may be deleted.from this monitoring program af ter (October 31) of the-year in which this land use census is j
conducted.
In lieu of a Licensee Event Re-port, identify the new location (s) in 'the i
next. Semiannual Radioactive Effluent Release I
Report 'and include the additions in the 0DCM.
4 i
I I
1 l
Amendment No.
50 1
_ ~.
1 i
LIMITING CONDITIONS FOR OPERATION:
SURVEILLANCE REQUIREMEhTS 4
6.3 INTERLABORATORY COMPARISON PROGRAM 6.3 INTERLABORATORY COMPARISON PROGRAM Applicability A summary of the resu.lts obtained as part of the above required Interlaboratory Comparison At all times.
Program shall be included in the Annual Radio-t logical Environmental Operating Report-(or par-Objective ticipants in the EPA cross-check program may provide the EPA program code designation for 3
To provide quality control of environmental the unit in lieu of providing the results).
4
' sample analyses.
Specifications T
- a. Analyses shall be performed on radioactive materials supplied-as part of an Interlab-oratory Coaiparison Program which has been approved by the Commission.
Participation in this program shall include all media for which samples are routinely collected and for which intercomparison samples are avail-l able.
i
- b. With analyses not being performed-as re-quired in 6.3.a above, report the corrective j
actions taken to prevent a recurrence in the Annual Radiological Environmental Operating
- Report, i
Amendment No.
51
BASES 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.1 MONITORING PROGRAM The radiological environmental monitoring program required by this speci-fication provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation.
This monitoring program assures that 10 CFR 50, Appendix I, Section IV.B.2 is met.
It thereby supplements the radiologi-cal effluent monitoring program by verifying that the measurable concen-trations of radioactive materials and levels of radiation are not higher than expectad, based on the effluent measurements and the modeling of the environmen'.al exposure pathways. The initial specified monitoring program will be effective for at least the first three years of commercial opera-tion.
Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limit of Detection (LLDs).
The LLDs re-quired by Table 6.1-3 are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system.
The LLD is not an a posteriori (after the fact) limit for a particular measurement.
6.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this cen-sus.
The best survey information, such as that from door to door sur-veys, aerial surveys, consultations with local agricultural authorities, etc., shall be used. This census satisfies the requirements of 10 CFR 50, Appendix I, Section IV.B.3.
Restricting the census to gardens of greater 2
than 50m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109, Revision 1, October 1977, for consumption by a child.
To determine this minimum garden size, the following assumptions were made:
(1) 20% of the garden was used for growing broad leaf vegetation (i.e.,
similar to lettuce and cabbage),
2 and, (2) a vegetable yield of 2 kg/m.
In lieu of the garden census the significance of the garden exposure pathway can be evaluated by the samp-ling of green leafy vegetables as specified in Table 6.1-1.
Amendment No.
52
BASES 6.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Pro-gram is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
Amendment No.
53
7.0 ADMINISTRATIVE CONTROLS 7.1 RESPONSIBILITY a.
The Resident Manager shall have direct responsibility for assuring the operation of the James A. FitzPatrick Plant is conducted in such a manner as to provide continuing protection to the environment.
During periods when the Resident Manager is unavailable, he may del-egate his responsibilities to the Superintendent of Power, or in his absence, to other qualified supervisory personnel.
b.
Implementation of the Radiological Effluent Technical Specifications is the responsibility of the Superintendent of Power, with the as-sistance of the plant staff organization.
7.2 PROCEDURES Written procedures and administrative policies shall be established, im-plemented and maintained that meet or exceed the requirements and recom-mendations of Section 5 " Facility Administrative Policies and Procedures" of ANSI 18.7-1972 and Regulatory Guide 1.33, November 1972, Appendix A.
In addition, procedures shall be established, implemented and maintained for the PCP, ODCM, and Quality Control Program for effluent and environ-mental monitoring using the guidance in Regulatory Guide 4.1, Revision 1.
7.3 REPORTING REQUIREMENTS a.
Planned Liquid and Gaseous Releases The limits for radioactive materials contained in liquid and gaseous effluents are contained in Specifications 2.3, 3.3 and 3.4.
b.
Environmental Samples Exceeding Limits of Table 6.1-2 When the limits of Table 6.1-2 are exceeded, refer to Specification 6.1.b for reporting requirements.
c.
Semiannual Radioactive Effluent Release Report Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be sub-mitted within 60 days after January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
1.
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 using as guidance Regu-latory Guide 1.21, Revision 1, June 1974, " Measuring, Evalu-ating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", with data summarized on a quarterly basis following the format of Appendix B there-of.
Amendment No.
54
2.
The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year may include an annual sum-mary ' of meteorological data collected over the previous year.
If the meteorological data is not included, the licensee shall retain it on file and provide it to the U.S. Nuclear Regulatory Commission upon request. This same report shall include an as-sessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year to the public. All assumptions used in making these assessments (i.e.,
specific activity, exposure time and location) shall be included in these reports.
The assessment of radiation doses shall be performed in accordance with the ODCM.
3.
The Radioactive Effluent Release Reports shall include any change to the PCP or the ODCM made during the reporting period.
4.
The Radioactive Effluent Release Report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycie sources (including doses from primary effluent pathways and direct radiation) during the previous calendar year, to show conformance with 40 CFR 190, Environmental Radiation Pro-tection Standards for Nuclear Power Operation. This assessment of radiation doses is performed in accordance with the ODCM and in lieu of the requirements contained in Regulatory Guide 1.21, Revision 1, June 1974, Appendix B, Section E.
5.
The Radioactive Effluent Release Reports shall include the following information for each class of solid waste shipped offsite during the report period:
Container volume; Total curie quantity (specify whether determined by mea-surement or estimate);
Principal radionuclides (specify whether determined by measurement or estimate);
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms);
Type of container (e.g., LSA, Type A, Large Quantity); and Solidification agent or absorbent (e.g.,
cement, Dow media, etc.).
6.
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases, to unrestricted areas of radioactive materials in gaseous and liquid effluents made dur-ing the reporting period.
Amendment No.
55
7.
The Radioactive Effluent Release Report shall contain the cause for unavailability of any environmental sample required by Table 6.1-1 and shall identify the locations for obtaining re-placement samples. This shall also include a revised figure (s) and table for the ODCM reflecting the new location (s).
Refer to Specification 6.1.c.
8.
The Radioactive Effluent Release Report shall contain new loca-tions identified in the - land use census in accordance with Specifications 6.2.b or 6.2.c.
9.
The Radioactive Effluent Release Report. shall contain the events leading to the condition which resulted in exceeding 10 curies for tanks specified in the Limiting Conditions for Operation, Section 2.5.a j
d.
Annual Radiological Environmental Operating Report Routine Radiological Environmental Reports covering the operation of the unit during the pervious calendar year shall be submitted prior to May 1 of each year.
The Annual Radiological Environmental Operating Reports shall in-f clude summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period.
The report shall include a comparison with preoperational studies, operational controls (as. appropriate), and environmental surveillance reports from the previous five years, and an assessment of'the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Specification 6.2.
The Annual Radiological Environmental Operating Reports shall in-clude the results of analysis of all radiological environmental samples and of all measurements taken during the period pursuant to Table 6.1-1, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radio-logical Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion in the report, the report shall note and explain the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: A summary description of the Radiological Environmental Monitoring Program; at least two legible maps
- covering all sampling locations and keyed to a table giving distances and directions from the centerline of the reactor; the results of participation in the Interlaboratory Comparison Pro-
, gram required by Specification 6.3 (or appropriate EPA cross-check program code), and discussion of all analyses in which the LLD's re-quired by Table 6.1-3 were not routinely achievable.
- One map shall cover stations near the site boundary; a second shall include i
the more distant stations.
Amendment No.
56 f
ATTACHMENT II PROPOSED CHANGES TO APPENDIX A ACCOMPANYING THE RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59
i 1
JAFNPP i
j Y.
Purge-Purging
}
Purge or Purging is the controlled process of discharging air or gas j
from a confinement in such a j
manner that replacement air or gas
{
is required to purify the confinement.
Z.
Venting 1
1 Venting is the controlled process of l
releasing air or gas form a con-finement in such a manner that re-l placement air or gas is not provided j
or required.
i i
j i
i i
i i
1 l
}
j Amendment NO.
6a i
JAFNPP 3.2 (cont'd) 4.2 (cont'd) controls are required to be operable as System logic shall be functionally specified in Specification 3.5.
tested as indicated in Table 4.2-2.
4 C.
Control Rod Block Actuation C.
Control Rod Block Actuation 1.
The limiting conditions of Instrumentation shall be functionally operation for the instrumentation tested, calibrated, and checked as that initiates control rod block indicated in Table 4.2-3.
are given in Table 3.2-3.
System logic shall be functionally 2.* The minimum number of operable tested as indicated in Table 4.2-3.
instrument channels specified in Table 3.2-3 for the rod block monitor may be reduced by one in one of the trip systems for main-tenance and/or testing, provided that this condition does not last longer than 24 hr. in any 30-day period.
1 D.
Radiation Monitoring Systems -
D.
Radiation Monitoring Systems -
Isolation & Initiation Functions Isolation and Initiation Functions 1.
Deleted 1.
Deleted.
2.
Standby Gas Treatment System 2.
Standby Gas Treatment System The limiting conditions for System logic shall be functionally 1
operation are given in Table tested as indicated in Table 4.2-4.
3.2-4.
I Amendment No.
50 1
i Page 51 intentionally left blank.
Amendment No.
51
Page 52 intentionally deleted.
, l Amendment No.
52
JAFNPP 3.2 (cont'd) 4.2 (cont'd) 3.
Deleted.
3.
Deleted 4.
Deleted.
4.
Deleted 5.
Main Control Room Ventilation 5.
Main Control Room Ventilation Isolation Isolation The limiting conditions for The i~nstrument surveillance operation are given on requirements are given on Table 3.2-4.
Table 4.2-4.
6.
Mechanical Vacuum Pump Isolation 6.
Mechanical Vacuum Pump Isolation (1)
The mechanical vacuum pump The instrument surveillance shall be capable of being requirements are given on Table automatically isolated and 4.2-4.
secured by a signal of high radiation in the main steam line tunnel whenever the main steam 1 solation valves are open.
(2)
If the limits of Table 3.2-4 are not met, the vacuum pump shall be isolated.
Amendment No.
53
3.2 DASES (cont'd)
C g',
the specific,ation are. adequate to assure the above criteria are met.
The opecification preserves the ef-(ectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of Inadvurtant oporation 1.e, only one inntriunent channel out of service.
Flou integrators are used to record the integrated flow of liquid from the. dry-well sumps. The alarm unit in each integrator is set to annunciate before the values specified in Speci-fication 3.6.D are exceeded.
For each parameter monitored, as listed in Table 3.2-6, by comparing the reading of each channel to the. reading on redundant or related instrument chgnnel a near continuous surveillance of instrument performance is available. Any deviation in readings will initiate any early recalibration thereby maintaining the quality of the instrument readings.
I 59 Amendment Aff
i JAFNPP Table 3.2-4 RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR' ISOLATE SYSTEMS Minimum of Total Number of Of Operable Instrument Channels 4
Instrument Provided By Design Action Channels (1)
Trip Function Trip Level Setting For Both Channels (2) 1 Main Control Room Ventilation s:4x103 cpm (6) 1 Inst. Channel A
Monitor 2
Mechanical Vacuum Pump Isolation 13 times normal full 4 Inst. Channels B
power background NOTES FOR TABLE 3.2-4 1.
Whenever the systems are required to be operable, there shall be two operable or tripped instrument channels per trip system.
From and after the time it is found that this cannot be met, the indicated action shall be taken.
i 2.
Action A.
Control Room Isolation is manually initiated.
UsessamesensorsasPrimaryContainmentIsolationonhighmainsteamlineradiation. Table 3.2-1.l B.
I 1
Amendment [,g 74
JAFNPP TABLE 4.2-4 MINUMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS i,
Instrument Channels Instrument Functional Test Calibration Instrument Check (2) (9) l
- 1) Mnin Control Room Ventilation Monitor (1)
Once/3 months Once/ day 2)
Mechanical Vacuum Pump Isolation (8)
Logic System Functional Test (4) (6)
Frequency 1)
Reactor Building Isolation
'Once/6 months 2)
Standby Gas Treatment System-Actuation Once/6 months 4
3)
Steam Jet Air Ejector Off-Gas Line Isolation Once/6 months 4)
Mechanical Vacuum Pump Isolation Once/ Operating Cycle Note:
See listing of notes following Table 4.2-6 for the notes referenced herein.
82 l
AmendmentNo.g
8.
R vicw ths Emerg ncy Plan and implcmenting procedures annually.
9.
Perform special review and/or investigations at the request of the Resident Manager.
10.
Review of those reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC, in accordance with Specification 6.9.
11.
Review the Of fsite Dose Calculation Manual (ODCM) and implementing procedures at least once per 24 months.
12.
Review the Process Control Program (PCP) at least once per 24 months.
(F)
Authority The PORC shall function to advise the Resident Manager on all matters related to nuclear safety and environmental operations.
The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 lE (1) through (4) and determine if items considered in 6.5 lE (1) through (5) constitute unreviewed safety questions, as defined in 10 CFR 50.59.
In the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the Sr. Vice President-Nuclear Generation or their designated alternates shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
(G) Records Minutes of all meetings of the PORC shall be recorded and numbered.
Copies will be retained in file. Copies will be forwarded to the Chairman of the SRC and the Sr. Vice President - Nuclear Generation.
(H) Procedures Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the pertinent Administrative Procedures.
6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall collectively have the competence required to review problems in the following areas:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control Am:ndment No.,E6 250
CHARTER 6.5.2.11. Conduct of the committee will be in accordance with a charter approved by the Senior Vice President-Nuclear Generation setting forth the mechanism for implementation of the committee's responsibilities and authority.
6.6. REPORTABLE OCCURRENCE ACTION (A)
In the event of a Reportable Occurrence, the NRC shall be notifiedand/orareportsubmittedpursuanttotherequirementsof Specication 6.9.
(B)
Each Reportable Occurrence requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC shall be reviewed timely by the PORC and a report submitted by the Resident Manager to the Senior Vice President-Nuclear Generation and the SRC.
6.7. SAFETY LIMIT VIOLATION (A) If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36 (c) (i).
(B) An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager.
The Senior Vice President-Nuclear Generation and Chairman of the SRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(C) The PORC shall prepare a complete investigative report of each safety limit violation and include appropriate analysis and evaluation of: (1) applicable circumstances preceding the occurrence; (2) effects of the occurrence upon facility component systems or structures; and (3) corrective action required to prevent recurrence.
The Resident Manager shall forward this report to the Senior Vice President-Nuclear Generation, Chairman of the SRC and the NRC.
6.8 PROCEDURES i
i (A) Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5 " Facility Administrative Policies and Procedures" of ANSI 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972.
In addition, procedures shall be established, implemented and maintained for the Fire Protection Program and other programs, as specified in Appendix B of these Technical Specifications, Section 7.2..
l (B) Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.
(C) Temporary changes to nuclear-related procedures may be made i
provided:
1.
The intent of the original procedure is not altered.
l Amendment No. pd, pf,)MI 253 1
6.16 Proccas Control Program (PCP)
A.
The PCP shall be a manual, as defined in Appendix B of these Technical Specifications, Section 1.0.
B.
The PCP shall be maintained at the plant consistent with these Technical Specifications and with approved plant procedures.
C.
Revisions of the PCP.
1.
Revisions of the PCP shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the revisions were made.
This submittal shall contain:
a.
sufficiently detailed information to support the rationale for the revisions without benefit of additional information.
b.
a determination that the revision did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
documentation that the revision has been reviewed and found acceptable by the PORC.
2.
Revisions of the PCP shall become effective upon issue following review and acceptance by the PORC.
D.
Temporary changes to the PCP may be made only ih accordance with the requirements of Section 6.8.C.
6.17.
Offsite Dose Calculation Manual (ODCM)
A.
The ODCM is defined in Appendix B of these Technical Specififications, Section 1.0.
B.
The ODCM shall be maintained at the plant and shall reflect accepted methodologies and calculational procedures.
C.
Revisions of the ODCM.
1.
Revisions of the ODCM shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the revisions were made effective.
This submittal shall contain:
a.
sufficiently detailed information to support the rationale for the revisions without benefit of additional information (information submitted shall consist of revised pages of the ODCM, with each page numbered and provided with an approval and date box, together with appropriate evaluations justifying the revisions).
258b Amendment No.
I J
b.
a datornination that the revisione will not reduce the cccuracy or reliability of dono calculations or setpoint determinations; and c.
documentation that the revisions have been reviewed and found acceptable by the PORC.
i 2.
Revisions of the ODCM shall become effective upon issue following review and acceptance by the PORC.
i f
D.
Temporary changes to the ODCM may be made only in accordance with the requirements of Section 6.8.C.
6.18 Major modifications to radioactive waste systems (liquid, gaseous and solid).
A.
Major modifications to radioactive waste systems shall be reported to the Commission in accordance with 10 CFR 50.59 or 10 CFR 50.71e.
258c Amendment No.
I l
ATTACHMENT III l
SAFETY EVALUATION FOR PROPOSED RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS AND ASSOCIATED CHANGES POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59
I.
Deacription of the Changno The proposed Radiological Effluent Technical Specifications (RETS) replace all of Appendix B of the FitzPatrick Technical Specifications.
Previcusly, non-radiological specifications in Appendix.B were deleted (Reference 1) with an amendment package approved by the'NRC
-(Reference 2).
The proposed RETS include or expand upon existing radiological specifications in Appendix B.
Subsection 2.3 of Appendix B,
" Radioactive Discharge," is replaced by RETS Sections 2.0 (Liquid Effluents) and 3.0 (Gaseous Effluents). Subsection 4.3 of Appendix B,
" Radiological Environmental Monitoring," is replaced by RETS Section 6.0 (Radiological Environmental Monitoring).
Section 5.0 of Appendix B,
" Administrative Controls," is replaced by RETS Section 7.0 (Administrative Controls).
The two organization charts now in Appendix B (Figures 5.2-1 and 5.2-2) are not included in the proposed RETS.
RETS contains additional sections which are not now
. included in Appendix B.
These are Section 4.0 (Solid Radioactive Waste) and Section 5.0 (Total Dose).
Furthermore, RETS refers to an Offsite Dose Calculation Manual (ODCM) for calculating offsite doses.
FitzPatrick's ODCM will be submitted to the NRC for' approval under a separate cover.
Several specifications in Appendix A are added, deleted or changed to accommodate the proposed RETS.
Two definitions, " Purge-Purging".and " Venting", are added to the definitions section on page 6a.
In Subsection 3.2.D on pages 50-53, all references to the Steam Air Ejector Offgas System, Radiation Monitoring Systems and Liquid'Radwaste Discharge are deleted.
Accordingly, the portions of the Bases addressing these items on page 59 are deleted.
In Table 3.2-4 on page 74, six of the eight monitor specifications-listed are deleted.
Similarly for Table 4.2-4 on page 82, four of the six monitor specifications listed are deleted, and one of the logic system functional test requirements is deleted.
These deleted specifications are now addressed in the proposed RETS.
In subsection 6.5.1.E on page 250, requirements for review of the ODCM and the FitzPatrick Process Control Program (as addressed in RETS Section 4.0) are added to the responsibilities of the Plant Operating Review Committee.
)
Reference is made, in Subesction 6.8A on page 253, to procedures specified in RETS Subsection 7.2.
Two new reporting requirements, for radioactivity in liquid holdup tanks and for offsite releases, are added on page 254e.
Lastly, three new subsections, regarding the Process Control Program, changes to the ODCM, and major modifications of radioactive waste systems, are added to the Administrative Controls section of Appendix A.
II. Purpose of the Changes The RETS and accompanying changes to Appendix A of the Technical Specifications are being proposed to assure that the requirements of 10 CFR 20 and 10 CFR 50, Appendix I, that radiological releases and doses be kept "as low as is reasonably achievable", are met.
III. Impact of the Changes The proposed RETS and accompanying changes to Appendix A are designed to further insure the health and safety of the public by requiring that radioactive effluent releases and offsite doses be kept as low as is reasonably achievable.
In many cases, RETS imposes radiological monitoring, analysis, control and reporting requirements over and above those now specified in Appendix B.
IV. Implementation of the Changes Implementation of the changes, as proposed, will not adversely impact the ALARA or Firc Protection programs at FitzPatrick.
Moreover, the changes will not adversely impact the environment.
V.
Conclusion The incorporation of these changes: a) will not increase the probability or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility of an accident or malfuntion of a type other than that evaluated previously in the Safety Analysis Report; c) will not reduce the margin of safety as defined in the basis for any Technical Specification; and d) does not constitute an unreviewed safety question.
l VI. Rnfarencss 1)
PASNY Letter, J.P.
Bayne to Domenic B.
Vassallo, dated February 10, 1983 (JPN-83-13).
2)
-NRC Letter, Domenic B. Vassallo to Leroy W. Sinclair, dated March 11, 1983 ([[::JAF-83-089|JAF-83-089]]).
3)
PASNY Proposed Radiological Effluent and Monitoring.
Technical Specifications, submitted by letter Paul J.
Early to Thomas A.
Ippolito, dated May 2, 1979 (JPN-79-26).
4)
NRC revised Technical Evaluation Report, " Comparison of Plant and Model Radiological Effluent Technical Specifications," transmitted by letter Domenic B.
Vassallo to Leroy W.
Sinclair, dated August 25, 1982 ([[::JAF-82-216|JAF-82-216]]).
5)
NRC NUREG-0473, Rev. 3, Draft 7",
" Standard Radiological Effluent Technical Specifications for Boiling Water Reactors," issued January 1983.
6)
PASNY letter, J.P.
Bayne to Domenic B.
Vassallo, dated November 22, 1982 (JPN-82-85).
7)
PASNY letter, J.
P.
Bayne to Domenic B.
- Vassallo, dated February 10, 1983 (JPN-83-12).
8)
PASNY letter, J.P.
Bayne to Domenic B.
Vassallo, dated March 9, 1983 (JPN-83-20).
j I
l