CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement
| ML17285A048 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/12/2017 |
| From: | Simril T Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNS-17-053 | |
| Download: ML17285A048 (38) | |
Text
(_~ DUKE ENERGY~
CNS-17-053 October 12, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01VP I 4800 Concord Road York, SC 29745 o: 803.701.3340 f-803.701.3221 tom.simril@duke-energy.com 2016 Annual Radioactive Effluent Release Report -Supplement
References:
- 1. Catawba Nuclear Station, Units 1 and 2, 2016 Annual Radioactive Effluent Release Report, dated April 27, 2017 (ADAMS Accession No. ML17128A429)
On April 27, 2017, Duke Energy submitted the 2016 Annual Radioactive Effluent Release Report for Catawba Nuclear Station (Reference 1) to the NRC. Attachment 9 (Summary of Changes to the Offsite Dose Calculation Manual) of this report states the entire Selected Licensee Commitment (SLC) Section 16.11 of the UFSAR is attached in the report. During a review, it was identified that the entire SLC Section 16.11 of the UFSAR was not submitted to the NRC per Station Technical Specification (TS) 5.5.5.b. The enclosure of this document supplements the inadvertently omitted sub-sections of SLC 16.11 for the period of January 1, 2016, through December 31, 2016. No revisions to the attached sections were made during this timeframe.
Any questions concerning this report should be directed to Cecil A. Fletcher II, Nuclear Regulatory Affairs Manager, at (803) 701-3622.
Sincerely,
- ()
loY"
' ~
Tom Simril Vice President, Catawba Nuclear Station
Enclosure:
Catawba Nuclear Station, Attachment 9, Summary of Changes to the Offsite Dose Calculation Manual, January 1, 2016, through December 31, 2016 www.duke-energy.com
United States Nuclear Regulatory Commission Page 2 CNS-17-053 October 12, 2017 xc (with enclosure):
C. Haney Regional Administrator U.S. Nuclear Regulatory Commission -Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 M. Mahoney NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 0-8H4A 11555 Rockville Pike Rockville, MD 20852-2738 J. D. Austin NRC Senior Resident Inspector Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12131/2016 Dose 16.11-3 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-3 Dose COMMITMENT The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 16.11-16-1 in SLC 16.11-16) shall be limited:
- a.
During any calendar quarter to:::_ 1.5 mrem to the whole body and to:::_ 5 mrem to any organ, and
- b.
During any calendar year to
- _ 3 mrem to the whole body and to~ 1 O mrem to any organ.
APPLICABILITY:
At a l
l times.
REMEDIAL ACTIONS A.
CONDITION Calculated dose from release of radioactive materials in liquid effluents exceeding above limits.
Catawba Units 1 and 2 A.1 REQUIRED ACTION
NOTE-------------
lf drinking water supply is taken from receiving water body within 3 miles downstream of plant discharge, the Special Report shall also include the results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to 40 CFR 141, Safe Drinking Water Act.
COMPLETION TIME Prepare and submit a 30 days Special Report to the NRC which identifies the causes for exceeding the limits, corrective actions taken to reduce releases, and actions taken to ensure that subsequent releases are within limits.
16.11-3-1 Revision 0 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Dose 16.11-3 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11-3-1 Determine cumulative dose contributions from liquid effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.
31 days BASES This SLC is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The COMMITMENT implements the guides set forth in Section II.A of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This SLC applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared radwaste treatment systems are used by more than one unit on a site, the wastes from a l
l units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the radwaste treatment system. For determining conformance to COMMITMENTS, these allocations from shared radwaste treatment systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.
Catawba Units 1 and 2 16.11-3-2 Revision O
REFERENCES
- 1.
Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12131/2016 Catawba Offsite Dose Calculation Manual.
- 2.
40 CFR Part 141.
- 3.
Catawba Units 1 and 2 16.11-3-3 Dose 16.11-3 Revision O Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Liquid Radwaste Treatment System 16.11-4 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-4 Liquid Radwaste Treatment System COMMITMENT The Liquid Radwaste Treatment System shall be FUNCTIONAL and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 16.11-16-1 in SLC 16.11-16) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY:
At all times.
REMEDIAL ACTIONS A.
CONDITION Radioactive liquid waste A.1 being discharged without treatment and in excess of above limits.
Any portion of Liquid Radwaste Treatment System not in operation.
Catawba Units 1 and 2 REQUIRED ACTION COMPLETION TIME Prepare and submit a 30 days Special Report to the NRC which identifies the reasons liquid radwaste was discharged without treatment, identification of non-functional equipment and reasons for non-functionality, corrective actions taken to restore the equipment to FUNCTIONAL status, and actions taken to prevent recurrence.
16.11-4-1 Revision 1 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Liquid Radwaste Treatment System 16.11-4 TESTING REQUIREMENTS
NOTE--------------------------------------------------------
The Liquid Radwaste Treatment System shall be demonstrated FUNCTIONAL by meeting SLC 16.11-1 and SLC 16.11-3.
TEST FREQUENCY TR 16.11-4-1 Project liquid release doses from each unit to UNRESTRICTED AREAS, in accordance with the methodology and parameters in the ODCM, when the Liquid Radwaste Treatment System is not being fully utilized.
31 days BASES The FUNCTIONALITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. 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 COMMITMENT implements the requirements of 1 O CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section 11.D of Appendix I to 1 O CFR Part 50. 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 Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
This SLC applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared radwaste treatment systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equalry to each of the radioactive waste producing units sharing the radwaste treatment system. For determining conformance to COMMITMENTS, these allocations from shared radwaste treatment systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
- 2.
Catawba Units 1 and 2 16.11-4-2 Revision 1 Summary of Changes to the Offsite Dose Calculation Manual REFERENCES (continued)
Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Liquid Radwaste Treatment System 16.11-4
- 3.
Catawba Units 1 and 2 16.11-4-3 Revision 1 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Chemical Treatment Ponds 16.11-5 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-5 Chemical Treatment Ponds COMMITMENT The quantity of radioactive material contained in each Chemical Treatment Pond (CTP) shall be limited by the following expression:
264 L A J
< 1.0 V
j (C1 xJO) excluding tritium and dissolved or entrained noble gases, where:
A i =
CTP inventory limit for single radionuclide "j", in Curies; C i =
10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", microCuries/milliliter; V ~design volume of liquid and slurry in the CTP, in gallons; and 264 = conversion unit, microCuries/Curie per milliliter/gallon.
APPLICABILITY:
At all times.
REMEDIAL ACTIONS A.
CONDITION Quantity of radioactive material in any CTP exceeding above limit.
A.1 REQUIRED ACTION Suspend all additions of radioactive material to the CTP.
COMPLETION TIME Immediately A.2 Initiate corrective action to Immediately reduce the CTP contents to within limits.
Catawba Units 1 and 2 16.11-5-1 Revision 0 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Chemical Treatment Ponds 16.11-5 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11-5-1 Verify that the quantity of radioactive material contained in each batch of resin/water slurry to be transferred to the CTPs is within limits by analyzing a representative sample of the batch to be transferred. Each batch to be transferred to the CTPs shall be limited by:
Prior to each transfer BASES L
c.
1-
< 0.006' j(C 1xl0) where:
c i = radioactive resin/water slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA CTPs, in microCuries/milliliter; and C
i =
10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", in microCuries/milliliter.
The inventory limits of the CTPs are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in this SLC assumes the pond inventory is uniformly mixed, that the pond is located in an uncontrolled area as defined in 10 CFR Part 20, and that the concentration limit in Note 1 to Appendix B of 10 CFR Part 20 applies.
The batch limits of resin/water slurry transferred to the CTP assure that radioactive material transferred to the CTP are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a. The expression in SLC 16.11-5 assures no batch will be transferred to the CTP unless the sum of the ratios of the activity of the radionuclides to their respective concentration limitation is less than the ratio of the 10 CFR Part 50, Appendix I, Section II.A, total body dose level to the instantaneous whole body dose rate limitation, or that:
L.
c i
< 3 mrem/yr =
O.OOS J (Ci x 10) 500 mrem/yr where:
Catawba Units 1 and 2 16.11-5-2 Revision 0 Summary of Changes to the Offsite Dose Calculation Manual BASES (continued)
Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Chemical Treatment Ponds 16.11-5 c i = radioactive resin/water slurry concentration for radionuclide "
j" entering the UNRESTRICTED AREA CTP, in microCuries/milliliter;
- and, Ci = 10 CFR Part 20, Appendix B, Table 2, Column 2, concentration for single radionuclide "j", in microCuries/milliliter.
The filter/demineralizers using powdered resin and the blowdown demineralizer are backwashed or sluiced to a holding tank. The tank will be agitated to obtain a representative sample of the resin inventory in the tank. A known weight of the wet, drained resin (moisture content approximately 55 to 60%, bulk density of about 58 pounds per cubic foot) will then be counted. The concentration of the resin slurry to be pumped to the CTPs will then be determined by the formula:
c. =
_a~i~w_R_
J v
T where:
Qi = concentration of radioactive materials in wet, drained resin for radionuclide "
j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58, and Co-60, in microCuries/gram. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent monthly composite analysis (within 3 months);
WR =total weight of resin in the storage tank in grams (determined from chemistry logs procedures); and, V r =total volume of resin water mixture in storage tank to be transferred to the CTPs in milliliters.
The batch limits provide assurance that activity input to the CTP will be minimized, and a means of identifying radioactive material in the inventory limitation of this SLC.
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
- 2.
- 3.
Catawba Units 1 and 2 16.11-5-3 Revision 0 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-6 Gaseous Effluents Gaseous Effluents 16.11-6 COMMITMENT The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 16.11-16-1 in SLC 16.11-16) shall be limited to the following:
- a.
For noble gases:,::. 500 mrem/yr to the whole body and,::. 3000 mrem/yr to the skin; and,
- b.
For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives > 8 days:,::. 1500 mrem/yr to any organ.
APPLICABILITY:
At a l
l times.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Dose rate not within limit.
A.1 Restore the release rate to Immediately within limits.
TESTING REQUIREMENTS TEST TR 16.11-6-1 Verify that the dose rate due to noble gases in gaseous effluents is within limits in accordance with the methodology and parameters in the ODCM.
TR 16.11-6-2 Verify that the dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents is within limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses according to Table 16.11-6-1.
Catawba Units 1 and 2 16.11-6-1 FREQUENCY In accordance with the methodology and parameters in the ODCM According to Table 16.11-6-1 Revision 3
Table 16.11-6-1 Radioactive Gaseous Waste Sampling and Analysis Program (page 1 of 4)
GASEOUS RELEASE TYPE SAMPLING MINIMUM TYPE OF ACTIVITY ANALYSIS FREQUENCY ANALYSIS FREQUENCY
- 1. Waste Gas Storage Tank Prior to each Prior to each Principal Gamma Emitters\\£)
release release Each Tank Each Tank Grab Sample
- 2. Containment Purge Prior to each Prior to each Principal Gamma Emittersl"J release release Each PURGE<3l Each PURGE<3l Grab Sample 31 days H-3 (oxide)
- 3. Unit Vent 7 daysl;jJ\\
4J 7 dayslJJ Principal Gamma Emittersl"J Grab Sample H-3 (oxide)
- 4. Containment Air Release and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />slJJl"J 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />slJJl"J Principal Gamma Emitters\\
2J Addition System Grab Sample 31 days H-3 (oxide)
- 5. All Release Types as Listed in 3.
ContinuouslbJ 7 daysl
'J 1-131 Above Charcoal Sample 1-133 Continuousl 0i 7 daysui Principal Gamma Emitters\\2J Particulate Sample Continuousl 0J 31 days Gross Alpha(HJ Composite Particulate Sample Cont inuous(bJ 92 days Sr-89, Sr-90 Composite Particulate Sample Catawba Units 1 and 2 16.11-6-2 Gaseous Effluents 16.11-6 LOWER LIMIT OF DETECTION (LLD)<
1l (µCi/ml) 1 x10-4 1x10 1x10-b 1x10 1x10-s 1x10-4 1x10-b 1 x10-'"
1 X1 o-IU 1x10_,,
1x10_,,
1x10-11 (continued)
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GASEOUS RELEASE TYPE SAMPLING MINIMUM TYPE OF ACTIVITY ANALYSIS FREQUENCY ANALYSIS FREQUENCY
- 6. Waste Monitor Tank Building 7 days 7 days Principal Gamma Em itters lLJ Ventilation Exhaust Grab Sample H-3 (oxide)
Continuousl 0J 7 days l
l jJ 1-131 Charcoal Sample 1-133 Continuous10' 7 days1g' Principal Gamma Emitters<£>
Particulate Sample Continuous10' 31 days Gross Alpha Composite Particulate Sample ContinuouslbJ 92 days Sr-89, Sr-90 Composite Particulate Sample Catawba Units 1 and 2 16.11-6-3 Gaseous Effluents 16.11-6 LOWER LIMIT OF DETECTION (LLD)(
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Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Table 16.11-6-1 Gaseous Effluents 16.11-6 Radioactive Gaseous Waste Sampling and Analysis Program (page 3 of 4)
NOTES:
(1)
The LLD is defined, for purposes of these commitments, 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% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
Where:
(2.71/T)+4.65sh LLD=
E
- V
- 2.22x10 6
- Y* exp(-Mt)
LLD =the "a priori" lower limit of detection (microCurie per unit mass or volume);
Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute);
E =the counting efficiency (counts per disintegration);
V = the sample size (units of mass or volume);
2.22 x 10 6 = the number of disintegrations per minute per microCurie; Y = the fractional radiochemical yield, when applicable; A. =the radioactive decay constant for the particular radionuclide (sec-1);
M = the elapsed time between midpoint of sample collection and time of counting (sec); and T =the sample counting time (min).
Typical values of E, V
, Y and.:
lt shall be used in the calculation.
It should be recognized that the LLD is defined as an §. priori (before the fact) limit representing the capability of a measurement system and not as an §. posteriori (after the fact) limit for a particular measurement.
Catawba Units 1 and 2 16.11-6-4 Revision 3 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Table 16.11-6-1 Gaseous Effluents 16.11-6 Radioactive Gaseous Waste Sampling and Analysis Program (page 4 of 4)
(2)
The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases based on grab samples and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, and Ce-141 in Iodine and particulate releases based on continuous samples. The LLD for Ce-144 is 5x10-9 µCi/ml and is based on continuous samples. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report, pursuant to Technical Specification 5.6.3 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
(3)
Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER stabilization (power level constant at desired power level) after a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, for at least one of the three gaseous release types with this notation.
(4)
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.*
(5)
Required sampling and analysis frequency during effluent release v ia this pathway.
(6)
The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLCs 16.11-6, 16.11-8, and 16.11-9.
(7)
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
(8)
The composite filter(s) will be analyzed for alpha activity by analyzing one filter per week to ensure that at least four filters are analyzed per collection period.
(9)
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to meet LLDs after changing, or after removal from sampler. If the particulate and charcoal sample frequency is changed to a 24-hour frequency, the corresponding LLDs may be increased by a factor of 10 (e.g., LLD for 1-131 from 1x10-12 to 1x10-11 µCi/ml).
Catawba Units 1 and 2 16.11-6-5 Revision 3
BASES Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Gaseous Effluents 16.11-6 The basic requirements for SLCs concerning effluents from nuclear power reactors are stated in 1 O CFR 50.36a. These requirements indicate that compliance with effluent SLCs will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1301 ). These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 1 O CFR 20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrems. It is further indicated in 1 O CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 1 O CFR 50, Appendix I.
As stated in the Introduction to Appendix B of the new 1 O CFR 20, the gaseous effluent concentration (EC) limits given in Appendix B, Table 2, Column 1, are based on an annual dose of 50 mrems for isotopes for which inhalation or ingestion is limiting or 100 mrems for isotopes for which submersion (noble gases) is limiting. Since release concentrations corresponding to limiting dose rates less than or equal to 500 mrems/year to the whole body, 3000 mrems/year to the skin from noble gases, and 1500 mrems/year to any organ from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days at the site boundary has been acceptable as a SLC limit for gaseous effluents to assure that the limits of 1 O CFR 50, Appendix I and 40 CFR 190 are not likely to be exceeded, it should not be necessary to restrict the operational flexibility by incorporating the dose rate associated with the EC value for isotopes based on inhalation/ingestion (50 mrems/year) or the dose rate associated with the EC value for isotopes based on submersion (100 mrems/year).
Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10 CFR 20, Appendix B, Table 2, Column 1, relate to a dose of 50 or 100 mrems in a year. When applied on an instantaneous basis, this corresponds to a dose rate of 50 or 100 mrems/year.
These low values are impractical upon which to base effluent monitor setpoint calculations for many gaseous effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.
Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrems/year to the whole body and 3000 mrems/year to the skin; and for lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate Catawba Units 1 and 2 16.11-6-6 Revision 3
BASES (continued)
Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Gaseous Effluents 16.11-6 form with half-lives greater than 8 days, an instantaneous dose rate limit of 1500 mrems/year to any organ.
Compliance with the limits of the new 1 O CFR 20.1301 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I and 40 CFR 190.
Operational history at Catawba has demonstrated that the use of the dose rate values listed above (i.e., 500 mrems/year, 3000 mrems/year, and 1500 mrems/year) as SLC limits has resulted in calculated maximum individual doses to MEMBERS OF THE PUBLIC that are small percentages of the limits of 1 O CFR 50, Appendix I and 40 CFR 190.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body and to less than or equal to 3000 mrem/year to the skin from noble gases, and to less than or equal to 1500 mrem/year to any organ from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days.
This commitment applies to the release of radioactive materials in gaseous effluents from all units at the site.
The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Based on NUREG-1301 and Regulatory Guide 1.21, the LLD value of 1x10-4 µCi/ml for grab samples is only applicable to noble gases grab samples and the LLD values for particulate and iodine radionuclides are applicable to continuous charcoal and particulate samples. The Table 16.11-6-1 Gaseous Release Type Number 5 (All Release Types as Listed in 3. Above) and Type Number 6 (Waste Monitor Tank Building Ventilation Exhaust) LLDs are based on weekly samples per NUREG-1301. There are two isotopes with associated LLDs that do not agree directly with NUREG-1301: Ce-144, LLD of 5x10-9
µCi/ml, which has historically been applied and achieved for analytical results, and 1-133, LLD of 1x10-10 µCi/ml, which again has been historically listed, as 1x10-9 µCi/ml, for Radioactive Gaseous Waste Sampling but changed to be in agreement with 1-131 for weekly (7-day) samples and is not specified in NUREG-1301. Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination -Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
Catawba Units 1 and 2 16.11-6-7 Revision 3 Summary of Changes to the Offsite Dose Calculation Manual REFERENCES (continued)
Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/3112016
- 2.
- 3.
- 4.
- 5.
40 CFR Part 190.
- 6.
- 7.
Catawba Units 1 and 2 16.11-6-8 Gaseous Effluents 16.11-6 Revision 3 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-7 Radioactive Gaseous Effluent Monitoring Instrumentation COMMITMENT The Radioactive Gaseous Effluent Monitoring Instrumentation channels shown in Table 16.11-7-1 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limits of SLC 16.11-6 are not exceeded.
The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
As shown in Table 16.11-7-1.
REMEDIAL ACTIONS
N 0 TE---------------------------------------------------
S ep~rate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more A.1 Suspend the release of Immediately Radioactive Gaseous radioactive gaseous Effluent Monitoring effluents monitored by the Instrumentation affected channel(s).
channel(s) Alarm/Trip Setpoint less OR conservative than required.
A.2 Declare the channel(s)
Immediately non-functional.
B.
One or more 8.1 Enter the applicable Immediately Radioactive Gaseous Conditions and Required Effluent Monitoring Actions specified in Table Instrumentation 16.11-7-1 for the channel(s) non-channel(s).
functional.
(continued)
Catawba Units 1 and 2 16.11-7-1 Revision 9 Summary of Changes to the Offsite Dose Calculation Manual REMEDIAL ACTIONS (continued)
C.
CONDITION One channel non-functional.
Catawba Units 1 and 2 Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 C.1 REQUIRED ACTION Verify that EMF-36 (Low Range) is FUNCTIONAL.
C.2.1 Analyze two independent samples of the tank's contents.
C.2.2 Perform independent verification of the discharge line valving.
C.2.3.1 Perform independent verification of manual portion of the computer input for release rate calculations performed by computer.
C.2.3.2Perform independent verification of entire calculations for release rate calculations performed manually.
C.2.4 Restore channel to FUNCTIONAL status.
C.3 Suspend release of radioactive effluents via this pathway.
16.11-7-2 COMPLETION TIME Prior to initiating a release Prior to initiating a release Prior to initiating a release Prior to initiating a
- release Prior to initiating a release 14 days Immediately (continued)
Revision 9 Summary of Changes to the Offsite Dose Calculation Manual REMEDIAL ACTIONS (continued)
CONDITION D.
One or more flow rate measurement device channel(s) non-functional.
E.
One or more Noble Gas Activity Monitor channel(s) non-functional.
Catawba Units 1 and 2 Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REQUIRED ACTION COMPLETION TIME D.1 Estimate the flow rate of Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the release.
during releases AND D.2 Restore channel to 30 days FUNCTIONAL status.
E.1 Obtain grab samples from Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> effluent pathway.
during releases AND E.2 Perform an analysis of Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of grab samples for obtaining the sample radioactivity.
AND E.3 Restore channel to 30 days FUNCTIONAL status.
(continued) 16.11-7-3 Revision 9 Summary of Changes lo the Offsi\\e Dose Calculation Manual REMEDIAL ACTIONS (continued)
CONDITION F.
Noble Gas Activity Monitor (EMF-39 -Low Range) providing automatic termination of release via the Containment Purge Exhaust System (CPES) non-functional.
G.
Required Action and associated Completion Time of Condition F not met.
OR Required Action F.1 not utilized.
Catawba Units 1 and 2 Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REQUIRED ACTION COMPLETION TIME F.1
N 0 TE-------------
In order to utilize Required Action F.1, the following conditions must be satisfied:
- 1. The affected unit is in MODES 5 or 6.
- 2. EMF-36 is FUNCTIONAL and in service for the affected unit.
- 3. The Reactor Coolant System for the affected unit has been vented.
- 4. Either the reactor vessel head is in place (bolts are not required),
or if it is not in place, the lifting of heavy loads over the reactor vessel and the movement of irradiated fuel assemblies within containment have been suspended.
Restore the non-functional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> channel to FUNCTIONAL status.
G.1 Suspend PURGING of Immediately radioactive effluents via this pathway.
(continued) 16.11-7-4 Revision 9 Summary of Changes to the Offsite Dose Calculation Manual REMEDIAL ACTIONS (continued)
CONDITION H.
One or more sampler channel(s) non-functional.
I.
One Condenser Evacuation System Noble Gas Activity Monitor (EMF-33) channel non-functional.
Catawba Units 1 and 2 Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REQUIRED ACTION COMPLETION TIME H.1 Perform sampling with Continuously auxiliary sampling equipment as required by Table 16.11-6-1.
AND H.2 Restore channel to 30 days FUNCTIONAL status.
1.1
N 0 TE------------
Applicable to effluent releases via the Condenser Steam Air Ejector (ZJ)
System.
Obtain grab samples from Once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s*
effluent pathway.
during releases AND 1.2
N 0 TE-----------
Applicable to effluent releases via the Condenser Steam Air Ejector (ZJ)
System.
Perform an analysis of Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of grab samples for obtaining the sample radioactivity.
AND (continued) 16.11-7-5 Revision 9 Summary of Changes to the Offsite Dose Calculation Manual REMEDIAL ACTIONS CONDITION I.
(continued)
J.
Noble Gas Activity Monitor (EMF-39 -Low Range) providing automatic termination of release via the Containment Air Release and Addition System non-functional.
Catawba Units 1 and 2 Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REQUIRED ACTION COMPLETION TIME 1.3
N 0 TE------------
Applicable to effluent releases via the Steam Generator Slowdown (BB)
System atmospheric vent valve (BB-27) in the off-normal mode.
Perform an analysis of Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples for during releases radioactivity at a lower limit when secondary of detection of 10-7 specific activity is >
microCurie/ml.
0.01 microCurie/gm DOSE EQUIVALENT 1-131 AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during releases when secondary specific activity is
~
0.01 microCurie/gm DOSE EQUIVALENT 1-131 AND 1.4 Restore channel to 30 days FUNCTIONAL status.
J.1 Verify that EMF-36 is Prior to initiating a FUNCTIONAL.
release OR J.2.1 Analyze two independent Prior to initiating a samples of the release containment atmosphere.
AND (continued) 16.11-7-6 Revision 9
REMEDIAL ACTIONS CONDITION J.
(continued)
Catawba Units 1 and 2 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REQUIRED ACTION J.2.2 Perform independent verification of the discharge line valving.
J.2.3.1 Perform independent verification of manual portion of the computer input for release rate calculations performed by computer.
J.2.3.2 Perform independent verification of entire calculations for release rate calculations performed manually.
AND J.2.4 ---------NOTE-----------
lf channel remains or is anticipated to remain non-functional for~ 90 days, re-evaluate the configuration of the affected unit in accordance with the applicable portions of 10 CFR 50.59 and 10 CFR 50.65(a)(4) prior to expiration of the 90-day period.
Restore channel to FUNCTIONAL status.
16.11-7-7 COMPLETION TIME Prior to initiating a release Prior to initiating a release Prior to initiating a release 30 days (continued)
Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 REMEDIAL ACTIONS (continued)
K.
CONDITION Required Action and associated Completion Time of Condition C, D, E, F, H, I, or J not met.
TESTING REQUIREMENTS K.1 REQUIRED ACTION Explain why the non-functionality was not corrected within the specified Completion Time.
COMPLETION TIME In the next scheduled Radioactive Effluent Release Report pursuant to Technical Specification 5.6.3
NOTE-----------------------------------------------------
Ref er to Table 16.11-7-1 to determine which TRs apply for each Radioactive Gaseous Effluent Monitoring Instrumentation channel.
TEST TR 16.11-7-1 Perform CHANNEL CHECK.
TR 16. 11-7 ------------------------------N 0 TE------------------------------
F or Instruments 1a, 4, and 5, a SOURCE CHECK for these channels shall be the qualitative assessment of channel response when the channel sensor is exposed to a light-emitting diode.
Perform SOURCE CHECK.
TR 16.11-7-3 Perform CHANNEL CHECK.
TR 16.11-7-4 Perform CHANNEL CHECK.
TR 16.11-7-5 Perform CHANNEL CHECK.
Catawba Units 1 and 2 16.11-7-8 FREQUENCY Prior to each release Prior to each release 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 24 hours 7 days (continued)
Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 TESTING REQUIREMENTS (continued)
TEST TR 16. 11-7 ------------------------------N 0 TE------------------------------
F or Instruments 2 and 3a, a SOURCE CHECK for these channels shall be the qualitative assessment of channel response when the channel sensor is exposed to a light-emitting diode.
Perform SOURCE CHECK.
TR 16. 11-7 ------------------------------N 0 TE------------------------------
F or Instruments 1a, 2, 3a, 3c, 5, and 6a, the COT shall also demonstrate, as applicable, that automatic isolation of this pathway and control room alarm annunciation (for EMF-58, alarm annunciation is in the Monitor Tank Building control room and on the Monitor Tank Building control panel remote annunciator panel) occur if any of the following conditions exist:
- a.
Instrument indicates measured levels above the Alarm/Trip Setpoint, or
- b.
Circuit failure/instrument downscale failure (alarm only)
Perform COT.
TR 16. 11-7-8 ------------------------------N 0 TE------------------------------
F or Instrument 4, the COT shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist:
- a.
Instrument indicates measured levels above the Alarm/Trip Setpoint, or
- b.
Circuit failure/instrument downscale failure (alarm only)
Perform COT.
Catawba Units 1 and 2 16.11-7-9 FREQUENCY 31 days 9 months 18 months (continued)
Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 111/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 TESTING REQUIREMENTS continued TEST TR 16. 11-7 -----------------------------N 0 TE------------------------------
F or Instruments 1a, 2, 3a, 3c, 4, 5, and 6a, the initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
Perform CHANNEL CALIBRATION.
Catawba Units 1 and 2 16.11-7-10 FREQUENCY 18 months Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 Table 16.11-7-1 Radioactive Gaseous Effluent Monitoring Instrumentation (page 1 of 2)
INSTRUMENT REQUIRED CONDITIONS APPLICABLE TESTING CHANNELS MODES REQUIREMENTS
- 1.
Waste Gas Holdup System 1.a Noble Gas Activity Monitor -Providing 1 per station A,C,K At all times except TR 16.11-7-1 Alarm and Automatic Termination of when the isolation TR 16.11-7-2 Release valve is closed and TR 16.11-7-7 (EMF-50-Low Range) locked TR 16.11-7-9 1.b Effluent System Flow Rate Measuring 1 per station D,K At all times except TR 16.11-7-1 Device when the isolation TR 16.11-7-9 valve is closed and locked
- 2. Condenser Evacuation System Noble A, I, K When air ejectors TR 16.11-7-3 Gas Activity Monitor are in operation TR 16.11-7-6 (EMF-33) (88-27 is only isolation (Apply Required TR 16.11-7-7 function required) (Note 1)
Action 1.3 when air TR 16.11-7-9 ejectors are not in operation)
- 3.
Vent System 3.a Noble Gas Activity Monitor A, E, K At all times TR 16.11-7-4 (EMF-36 -Low Range)
TR 16.11-7-6 TR 16.11-7-7 TR 16.11-7-9 3.b Deleted.
3.c Particulate Sampler A,H, K At all times TR 16.11-7-4 (EMF-35)
(Note 2)
TR 16.11-7-6 TR 16.11-7-7 TR 16.11-7-9 3.d Unit Vent Stack Flow Rate Meter D, K At all times TR 16.11-7-4 (no alarm/trip function)
(Note 2)
TR 16.11-7-9 3.e Unit Vent Radiation Monitor Flow Meter E, K At all times TR 16.11-7-4 (Note 2)
TR 16.11-7-9 4
. Containment Purge System Noble Gas A,F,G, K 5,6 TR 16.11-7-2 Activity Monitor -Providing Alarm and TR 16.11-7-3 Automatic Termination of Release TR 16.11-7-8 (EMF-39-Low Range)
TR 16.11-7-9 (continued)
Catawba Units 1 and 2 16.11-7-11 Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 Table 16.11-7-1 Radioactive Gaseous Effluent Monitoring Instrumentation (page 2 of 2)
INSTRUMENT
- 5.
Containment Air Release and Addition System Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release (EMF-39 -Low Range)
- 6.
Monitor Tank Building HVAC 6.a Noble Gas Activity Monitor -Providing Alarm (EMF-58 -Low Range) 6.b Effluent Flow Rate Measuring Device REQUIRED CHANNELS 1 per station 1 per station CONDITIONS A, J, K A,E,K D,K APPLICABLE MODES 1,2, 3,4, 5,6 At all times (Note 2)
At all times (Note 2)
Note 1: The setpoint is as required by the primary to secondary leak rate monitoring program.
TESTING REQUIREMENTS TR 16.11-7-2 TR 16.11-7-3 TR 16.11-7-7 TR 16.11-7-9 TR 16.11-7-4 TR 16.11-7-6 TR 16.11-7-7 TR 16.11-7-9 TR 16.11-7-4 TR 16.11-7-9 Note 2: Except when the effluent pathway is mechanically isolated; thus, a release to the environment is not possible.
Catawba Units 1 and 2 16.11-7-12 Revision 9
BASES Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 The Radioactive Gaseous Effluent Monitoring Instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of SLC 16.11-8 shall be such that concentrations as low as 1 x 10-6 µCi/cc are measurable.
Regarding Note 2 of Table 16.11-7-1, isolation of the effluent pathway is to be by mechanical means (e.g., valve closure). Electrical or pneumatic isolation is not required, unless the isolation is designed to receive an automatic signal to open.
In MODES 5 and 6, initiation of the Containment Purge Exhaust System (CPES) with EMF-39 non-functional is not permissible. The basis for Required Action F.1 is to allow the continued operation of the CPES with EMF-39 initially FUNCTIONAL. Continued operation of the CPES is contingent upon the ability of the affected unit to meet the requirements as noted in Required Action F.1.
TR 16.11-7-7 requires the. performance of a COT on the applicable Radioactive Gaseous Effluent Radiation Monitors. The test ensures that a signal from the control room module can generate the appropriate alarm and actuations. The required actuations/isolations for a High Radiation condition (i.e., radiation level above its Trip 2 setpoint) are listed below for each monitor.
OEMF-50 -Waste Gas Discharge Monitor 1WG160 closes when EMF-50 detects radiation level above its setpoint.
1/2EMF-33 -Condensate Steam Air Ejector Exhaust Monitor The following actuations occur when EMF-33 detects radiation level above its set point:
- 1.
Closure of 8827 is required in order to isolate the Slowdown Tank from the environment. Because of plant limitations/restrictions:
- a.
Opening the valve (in order to verify it goes closed on a High Radiation signal) is only possible during outages due to the negative effects on the Slowdown System with the unit at power.
- b.
Testing during innages will be by verification of relay contacts opening in the valve circuit.
- 2.
Closure of 8824, 8865, 8869, and 8873 is required to minimize the amount of potentially contaminated material being delivered to the Slowdown Tank.
- 3.
Closure of NM269, NM270, NM271, and NM272 is required to minimize the amount of potentially contaminated material being delivered to the Conventional Sampling System.
- 4.
Closure of NM267 is required to minimize the amount of potentially contaminated material being delivered to the Condensate Storage Tank by isolating flow through EMF-34.
Catawba Units 1 and 2 16.11-7-13 Revision 9 Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7 BASES (continued)
- 5.
Closure of 8848 is required to minimize the amount of potentially contaminated material being delivered from the Slowdown System discharge to the Turbine Building sump.
1/2EMF-36 -Unit Vent Noble Gas Monitor The following actuations occur when EMF-36 detects radiation level above its setpoint:
- 1.
Containment Air Release and Addition System fans discharge to unit vent valve VQ10 closes.
- 2.
Auxiliary Building unfiltered ventilation exhaust fans A and B stop.
- 3.
Fuel Handling Ventilation Exhaust System (FHVES) exhaust trains align to the filter units.
- 4.
(For 1EMF-36 only) 1WG160 closes.
1/2EMF-35 -Unit Vent Particulate Monitor (Sampler)
The following actuations occur when EMF-35 detects radiation level above its setpoint:
- 1.
Containment Air Release and Addition System fans discharge to unit vent valve VQ10 closes.
- 2.
Auxiliary Building unfiltered ventilation exhaust fans A and B stop.
- 3.
Fuel Handling Ventilation E~haust System (FHVES) exhaust trains align to the filter units.
- 4.
((For 1EMF-35 only) 1WG160 closes.
1/2EMF-39 -Containment Noble Gas Monitor The following actuations occur when EMF-39 detects radiation level above its setpoint:
- 1.
Signals are provided to both trains of the Solid State Protection System (SSPS) to initiate a CPES isolation. This is verified by observing that Relays K615 in the SSPS A output cabinet and the SSPS B output cabinet are latched.
- 2.
EMF-39 isolates the CPES without going through the SSPS by stopping CPES supply fans A and B, CPES exhaust fans A and B, and by closing the appropriate valves and dampers.
- 3.
Containment Evacuation Alarm, unless the source range trip is blocked.
OEMF-58 This monitor provides no control function.
TR 16.11-7-8 requires the performance of a COT on the Containment Noble Gas Monitor, 1/2EMF-39. The test ensures that a signal from the control room module can generate the appropriate alarm and actuations. The required actuations/isolations for a High Radiation condition (i.e., radiation level above its Trip 2 setpoint) are listed below.
1/2EMF-39 -Containment Noble Gas Monitor The following actuations occur when EMF-39 detects radiation level above its setpoint:
Catawba Units 1 and 2 16.11-7-14 Revision 9
BASES (continued)
Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11-7
- 1.
Signals are provided to both trains of the Solid State Protection System (SSPS) to initiate a Containment Air Release and Addition System isolation. This is verified by observing that relays K615 in the SSPS Train A output cabinet and the SSPS Train B output cabinet are latched.
- 2.
Containment Evacuation Alarm, unless the source range trip is blocked.
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
- 2.
Catawba Units 1 and 2 16.11-7-15 Revision 9 Summary of Changes to the Off site Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Dose -Noble Gases 16.11-8 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-8 Dose -Noble Gases COMMITMENT The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-16-1 in SLC 16.11-16) shall be limited to the following:
- a.
During any calendar quarter: ~ 5 mrad for gamma radiation and,:: 1 O mrad for beta radiation, and
- b.
During any calendar year:,:: 1 O mrad for gamma radiation and
~ 20 mrad for beta radiation.
APPLICABILITY:
At a l
l times.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated air dose from A.1 radioactive noble gases Prepare and submit a 30 days in gaseous effluents exceeding any of above limits.
TESTING REQUIREMENTS TEST Special Report to the NRC which identifies the causes for exceeding the limits, corrective actions taken to reduce releases, and actions taken to ensure that subsequent releases are within limits.
TR 16.11-8-1 Determine cumulative dose contributions from noble gases in gaseous effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.
Catawba Units 1 and 2 16.11-8-1 FREQUENCY 31 days Revision 0
BASES Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12131/2016 Dose -Noble Gases 16.11-8 This SLC is provided to implement the requirements of Sections 11.B, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The COMMITMENT implements the guides set forth in Section 11.B of Appendix I. The REMEDIAL ACTION statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The TESTING REQUIREMENTS implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 O CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared radwaste treatment systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactives waste producing units sharing the radwaste treatment system. For determining conformance to COMMITMENTS, these allocations from shared radwaste treatment systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
- 2.
Catawba Units 1 and 2 16.11-8-2 Revision O Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016-12/31/2016 Dose -lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form 16.11-9 16.11 RADIOLOGICAL EFFLUENTS CONTROLS 16.11-9 Dose-lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form COMMITMENT The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-16-1 in SLC 16.11-
- 16) shall be limited to the following:
- a.
During any calendar quarter: s 7.5 mrem to any organ, and
- b.
During any calendar year: s 15 mrem to any organ.
APPLICABILITY:
At all times.
REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Calculated dose from A
.1 Prepare and submit a 30 days the release of lodine-131, lodine-133, tritium, and radioactive material in particulate form with half-lives > 8 days in gaseous effluents exceeding any of above limits.
TESTING REQUIREMENTS TEST Special Report to the NRC which identifies the causes for exceeding the limits, corrective actions taken to reduce releases, and actions taken to ensure that subsequent releases are within limits.
TR 16.11-9-1 Determine cumulative dose contributions from lodine-131, lodine-133, tritium, and radioactive material in particulate form with half-lives > 8 days in gaseous effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.
Catawba Units 1 and 2 16.11-9-1 FREQUENCY 31 days Revision 0
BASES Summary of Changes to the Offsite Dose Calculation Manual Catawba Nuclear Station Units 1 & 2 Period 1/1/2016 -12/31/2016 Dose -lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form 16.11-9 This SLC is provided to implement the requirements of Sections 11.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50, and are the guides set forth in Section 11.C of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the TESTING REQUIREMENTS implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate COMMITMENTS for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared radwaste treatment systems are used by more than one unit on a site, the wastes from a l
l units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the radwaste treatment system. For determining conformance to COMMITMENTS, these allocations from shared radwaste treatment systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.
REFERENCES
- 1.
Catawba Offsite Dose Calculation Manual.
- 2.
Catawba Units 1 and 2 16.11-9-2 Revision O