ML15086A211
| ML15086A211 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/10/2015 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15086A176 | List: |
| References | |
| W3F1-2015-0023 | |
| Download: ML15086A211 (31) | |
Text
3/4 11-1AMENDMENT NO. 02, 51 (DRN 02-216)3/4.11 RADIOACTIVE EFFLUENTS (See note below) (DRN 02-216)3/4.11.1 LIQUID EFFLUENTSCONCENTRATIONLIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluentsto UNRESTRICTED AREAS (TS Figure 5.1-3) shall be limited to ten times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X
10-4 microcurie/ml total activity.APPLICABILITY: At all timesACTION:With the concentration of radioactive material released in liquid effluents to UNRESTRICTEDAREAS exceeding the above limits, immediately restore the concentration to within the above limits, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the samplingand analysis program of Table 4.11-1.4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with themethodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Requirement 3.11.1.1. (DRN 02-216)NOTE: TRM Specifications 3.11.1.1 and 4.11.1.1.1 are part of the Offsite Dose CalculationManual (ODCM), reference UNT-005-014. Revision of these TRM Specifications requires theapproval of the General Manager Plant Operations (GMPO) in accordance with TechnicalSpecification 6.14. (DRN 02-216) 3/4 11-2AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]BATCH RELEASES [d]1. Boric Acid Condensate TanksGrab sample from each batchPrior toGamma Emitters [b](4 Tanks)to be released prior toreleaseI-131releaseNoble GasesA Composite [c] of all grabMonthlyH-3samples collected during theGross Alphamonth for this release pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for his releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-3AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]BATCH RELEASES [d]2. Liquid Waste Management TanksGrab sample from each batchPrior toGamma Emitters [b][2 Waste Condensate Tanksto be released prior toreleaseI-131 2 Laundry TanksreleaseNoble Gases 3 Waste Tanks]A Composite [c] ofMonthlyH-3all grab samplesGross Alphacollected during the month for this release
pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for this releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-4AMENDMENT NO. 02,51 , 53 (DRN 02-216)
TABLE 4.11-1 (Continued, See note below)(DRN 02-216)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPESAMPLE TYPE ANDANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCYANALYSIS [a]
BATCH RELEASES [d,g]3. Secondary Plant Holding Tanks [f]Grab sample from each batchPrior toGamma Emitters [b][Regenerative Waste Tank andto be released prior to release I-131 Filter Flush Tank]
release Noble Gases H-34. Turbine Building Industrial Waste Grab sample from each batchPrior toGamma Emitters [b]
Sumps (2 Sumps) [TBIWS]to be released prior to release I-131 release Noble Gases (DRN 02-357)For applicability, see note [i] and [p](DRN 02-357)
A Composite [c] of all grabMonthlyH-3 samples collected during theGross Alpha month for this release
pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90 quarter for this release Fe-55 point(DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl e requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14.(DRN 02-216) 3/4 11-5AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]BATCH RELEASES [d, g]5. Dry Cooling Tower Sumps #1 and #2 [DCTS]Grab sample from each batchPrior toGamma Emitters [b]to be released prior toreleaseI-131 releaseNoble GasesFor applicability, see note [j]A Composite [c] of allMonthlyH-3grab samples collectedGross Alphaduring the month for this release pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for this releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-6AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]BATCH RELEASES [d, g]6. Steam Generator BlowdownGrab sample from each batchPrior toGamma Emitters [b]to be released prior toreleaseI-131 releaseNoble GasesFor applicability, see note [k & 1]A composite [c] of all grabMonthlyH-3samples collected during theGross Alphamonth for this release pointA Composite [c] of all grabQuarterlySr-89samples collected duringSr-90the quarter for this releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-7AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]BATCH RELEASES [d, g]7. Auxiliary Component Cooling WaterGrab sample from each batchPrior toGamma Emitters [b]System [ACCW] (2 Basins)to be released prior toreleaseI-131release:Noble GasesFor applicability, see note [n]A Composite [c] of all grabMonthlyH-3samples collected during theGross Alphamonth for this release
pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for this releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-8AMENDMENT NO. 51 , 53 (DRN 02-216)
TABLE 4.11-1 (Continued, See note below) (DRN 02-216)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPESAMPLE TYPE ANDANALYSIS TYPE OF AND RELEASE POINT FREQUENCY FREQUENCY ANALYSIS [a]
CONTINUOUS RELEASES [e, h]1. Turbine Building Industrial WasteWeekly grab sampleWeeklyGamma Emitters [b]
I-131 Noble Gases(DRN 02-357)For applicability, see note [i] and [p]A Composite [c] of all grabMonthlyH-3 (DRN 02-357) samples collected during theGross Alpha month for this release pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90
quarter for this release Fe-55 point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl e requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-9AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]CONTINUOUS RELEASES [e, h]2. Dry Cooling Tower Sumps #1 and #2 [DCTS]Weekly grab sampleWeeklyGamma Emitters [b]I-131 Noble GasesFor applicability, see note [j]A Composite [c] of allMonthlyH-3grab samples collectedGross Alphaduring the month for this release pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for this releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-10AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]CONTINUOUS RELEASES [e, h]3. Circulating Water Discharge - SteamWeekly grab sampleWeeklyGamma Emitters [b]Generator Blowdown Heat Exchanger DischargeI-131
[CWD]Noble GasesFor applicability, see note [o]A Composite [c] of all grabMonthlyH-3samples collected during theGross Alphamonth for this release
pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for each releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-11AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]CONTINUOUS RELEASES [e, h]4. Auxiliary Component Cooling WaterWeekly grab sampleWeeklyGamma Emitters [b]System [ACCW] 2 Basins)I-131Noble GasesA Composite [c] of all grabMonthlyH-3samples collected during theGross AlphaFor applicability, see note [n]month for this release pointA Composite [c] of all grabQuarterlySr-89samples collected during theSr-90quarter for each releaseFe-55
point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-12AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAMLIQUID RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS [a]CONTINUOUS RELEASES [e, h]5. Steam Generator BlowdownContinuous [m] sampleWeeklyGamma Emitters [b]collected weeklyI-131Noble GasesFor applicability, see note [k & 1]A Composite [c] of allMonthlyH-3weekly samples collectedGross Alphaduring the month for this release pointA Composite [c] of allQuarterlySr-89weekly samples collectedSr-90during the quarter for thisFe-55 release point (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Tabl erequires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-13AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-1 (Continued, See note below) (DRN 02-216)TABLE NOTATIONSa.The type of analysis and their associated Lower Limits of Detection (LLD),as defined in the ODCM, are: (DRN 02-216) (DRN 02-216)Type of AnalysisLLD (µCi/ml)Gamma Emitters5E-07I-1311E-06 Noble Gases (Gamma Emitters)1E-05 H-31E-05 Gross Alpha1E-07 Fe-551E-06 Sr-89, Sr-905E-08 Ce-1445E-06b.The gamma emitters LLD Requirement includes the following radionuclides:MN-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Theanalysis for gamma emitters shall include an analysis for I-131 and gamma emitting noble gases dissolved or entrained in the sample at the LLD's specified above. This list does not mean that only these nuclides are to be considered. Other identifiable gamma peaks, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.c.A composite sample is one in which the quantity of liquid sampled isproportional to the quantity of liquid waste discharged and in which the method ofsampling employed results in a specimen that is representative of the liquids released.
Prior to analyses, all samples taken for composites are to be thoroughly mixed in order for the composite sample to be representative of the effluent release.d.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 mixedto assure representative sampling.e.A continuous release is the discharge of liquid wastes of a non-discretevolume, e.g., a system that has input flow during the release (in service sumps, etc). (DRN 02-216)Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager PlantOperations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-14AMENDMENT NO. 51 , 53 (DRN 02-216)
TABLE 4.11-1 (Continued, See note below) (DRN 02-216)
TABLE NOTATIONS (DRN 02-357)f.If the contents of the Regenerative Waste Tank or Filter Flush Tank contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA, and the contents of these tanks shall be directed to the Liquid Waste Management System or other monitored effluent release point. (DRN 02-357)g.When release from this source is batch in nature.h.When release from this source is continuousin nature.i.TheTurbine Building Industrial Waste Sumps (TBIWS) shall be sampled and analyzed in accordance with this table if any of the following conditions exist, and the release has NOT been directed to the Liquid Waste Management System:(1)Primary to Secondary leakage is occurring: or,(2)Activity is present in the secondary system as indicated by either the Steam Generator Blowdown (SGB) monitor or secondary sampling and analysis; or,(3)Activity was present in the TBIWS during the previous FOUR Weeks.j.The Dry Cooling Tower Sump (DCTS) shall be sampled and analyzed in accordance with this table if any of the following conditions exist, and the release has NOT been directed to the Liquid Waste Management System:(1)Primary to Component Cooling Water (CCW) leakage is occurring or, (2)Activity is present in the CCW/ACCW systems as indicated by either the CCW monitors or CCW/ACCW sampling and analysis; or,(3)Activity was present in the DCTS during the previous FOUR W eeks.k.Sampling and analysis of Steam Generator Blowdown will be required onlywhenblowdown is directed to the Circulating Water System (CWS) or the Waterford Waste Ponds. (DRN 02-216)
Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-15AMENDMENT NO. 51 , 53 (DRN 02-216)
TABLE 4.11-1 (Continued, See note below) (DRN 02-216)
TABLE NOTATIONSl.Steam Generator Blowdown discharge to the Waste Ponds shall not be performed unless radiation monitoring and automatic isolation capabilities are added to the Waste Ponds discharge path. Steam Generator Blowdown to the Waste Ponds will be
limited to situations requiring secondary chemistry control where the Circulating Water
System is not available or the secondary chemistry is outside the requirements for
Circulating Water System discharge.
Blowdown to the Waste Ponds will be terminated upon detection of sample activity greater than the LLD levels in Notation [a].m.To be representative of the quantities and concentration of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate
of flow of the effluent stream.n.Sampling and analysis of the Auxiliary Component Cooling Water (ACCW)system is required when detectable activity exists in the CCW system. Continued sampling and analysis of ACCW is required for a minimum of FOUR Weeks following non-detection of activity in CCW/ACCW systems.o.Sampling and analysis of the Circulating Water Discharge - Steam Generator Blowdown heat exchanger discharge (CWD) is required when detectable activity exists in the secondary system, or the CCW/ACCW Systems. (DRN 02-357)p.The normal sampling location is the Oil Separator System, which receives all TBIWS wastewater, and is the release path to the Unrestricted Area. (DRN 02-357) (DRN 02-216)
Note: TRM Table 4.11-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-16 AMENDMENT NO. 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.1 LIQUID EFFLUENTS
DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive
materials in liquid effluents released to UNRESTRICTED AREAS (see TS Figure 5.1-3) shall be
limited: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY
- At all times.
ACTION: With the calculated dose from the release of radioactive materials in
liquid effluents exceeding any of the above limits, prepare and submit to the Commission within
30 days, pursuant to Technical Specification 6.9.2, a Special Report. This Special Report shall:
(1) Identify the cause(s) for exceeding the limit(s) and define the corrective actions that have
been taken to reduce the releases and the proposed corrective actions to be taken to assure
that subsequent releases will be in compliance with the above limits. NOTE
- The following step is applicable only if drinking water supply is taken from the receiving water. (2) Include the
results of radiological analyses of the drinking water source and the radiological impact on
finished drinking water supplies with regard to the requirements of 40 CFR Part 141.
(DRN 04-1191, Am. 91)
The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter
and the current calendar year shall be determined in accordance with methodology and
parameters specified in the ODCM at least once per 31 days.
NOTE: TRM Specification 3.11.1.2 is part of the Offsite Dose Calculation Manual (ODCM),
reference UNT-005-014. Revision of this specification requires the approval of the General
Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216)
3/4 11-17 AMENDMENT NO. 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.1 LIQUID EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate
portions of the system shall be used to reduce releases of radioactivity when the projected doses due
to the liquid effluent to UNRESTRICTED AREAS (see TS Figure 5.1-3) would exceed in a 31 day
period: a) 0.06 mRem to the total body, or b) 0.2 mRem to any organ APPLICABILITY
- At all times.
ACTION: With radioactive liquid waste being discharged without treatment and in excess of the above limits
and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and
submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report
that includes the following information.
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and, 3. Summary description of action(s) taken to prevent a recurrence.
(DRN 04-1191, Am. 91)
The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once
per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.1.3.2 The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated
OPERABLE by meeting Requirements 3.11.1.1 and 3.11.1.2
NOTE: TRM Section 3.11.1.3 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-
005-014. Revision of this TRM specification requires the approval of the General Manager Plant
Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216)
3/4 11-18AMENDMENT NO. 51 (DRN 02-216)3/4.11 RADIOACTIVE EFFLUENTS (See note below) (DRN 02-216)3/4.11.2 GASEOUS EFFLUENTSDOSE RATELIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the siteto areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-3) shall be limited to the following:a.For Noble gases: Less than or equal to 500 mrem/yr to thetotal body; and 3000 mrem/yr to the skin, andb.For Iodine-131, Iodine-133, Tritium, and all radionuclides inparticulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ.APPLICABILITY: At all times.ACTION:With the dose rate(s) exceeding the above limits, immediately restore the release rate to withinthe above limit(s), and describe the events leading to this condition in the next AnnualRadioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS: 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to bewithin the above limits in accordance with the methodology and parameters in the ODCM.4.11.2.1.2 Representative samples and analysis of gaseous effluents shall be obtained inaccordance with the sampling and analyses program specified in Table 4.11-2.4.11.2.1.3 Based upon the sampling and analysis performed in Table 4.11-2 the dose rate dueto I-131, I-133, H-3, and all other radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. (DRN 02-216)NOTE: TRM Specifications 3.11.2.1 and 4.11.2.1.2 are part of the Offsite Dose CalculationManual (ODCM), reference UNT-005-014. Revision of these TRM Specifications requires theapproval of the General Manager Plant Operations (GMPO) in accordance with TechnicalSpecification 6.14. (DRN 02-216) 3/4 11-19AMENDMENT NO. 02, 51 (DRN 02-216)TABLE 4.11-2 (See note below) (DRN 02-216)RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMGASEOUS RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS(a)1. Waste Gas Decay TanksGrab sample from each tankPrior toNoble Gas(3 Tanks)to be released prior toReleaseGamma Emitters [b]release2. Containment Purge (Plant Stack)Grab sample from each purgePrior toNoble Gasprior to releaseRelease [g]Gamma Emitters [b]
Grab sample prior to purgePrior toH-3[i]Release[i, g]Continuous noble gas monitorContinuousNoble GasesGross Beta orGamma (DRN 02-216)NOTE: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requiresthe approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-20AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-2 (See note below) (DRN 02-216)RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMGASEOUS RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS(a)3. Plant StackMonthly grab sampleMonthly [g]Noble GasGamma Emitters [b]MonthlyH-3[f, g]Continuous CharcoalWeekly [h]I-131Cartridge Sample [c]I-133 ContinuousWeekly [h]ParticulateParticulate Sample [c]Gamma Emitters [b]Gross AlphaComposite of all continuousparticulate filtersQuarterlySr-89collected during the QuarterSr-90Continuous noble gasContinuousNoble GasesmonitorGross Beta orGamma (DRN 02-216)Note: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires theapproval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-21AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-2 (Continued, See note below) (DRN 02-216)RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMGASEOUS RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS (a)4. Fuel Handling Building VentilationMonthly grab sampleMonthlyNoble Gas(Normal Exhaust)gamma Emitters [b]Weekly grab sampleWeeklyH-3Continuous CharcoalWeeklyI-131Cartridge Sample[c]I-133Continuous ParticulateWeeklyParticulate Sample [c]Gamma Emitters[b]Gross AlphaWhenever irradiated fuel is in the storageComposite of allQuarterlySr-89pool, see note [e]continuous particulateSr-90filters collected during the QuarterContinuous noble gasContinuousNoble Gases GrossmonitorBeta or Gamma (DRN 02-216)Note: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires theapproval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-22AMENDMENT NO. 51 (DRN 02-216)TABLE 4.11-2 (Continued, See note below) (DRN 02-216)RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAMGASEOUS RELEASE TYPESAMPLE TYPE ANDANALYSISTYPE OFAND RELEASE POINTFREQUENCYFREQUENCYANALYSIS (a)5. Main Condenser Evacuation and TurbineMonthly grab sampleMonthly[g]Noble GasGland Sealing System (MCES)Gamma Emitters [b]Monthly [g]H-3For applicability see note [d]Continuous CharcoalWeekly [h]I-131Cartridge Sample [c]I-133Continuous ParticulateWeekly [h]ParticulateSample [c]Gamma Emitters [b]Gross AlphaComposite of all continuousQuarterlySr-89particulate filtersSr-90collected during the QuarterContinuous noble gas monitorContinuousNoble Gases GrossBeta or Gamma (DRN 02-216)Note: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires theapproval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-23AMENDMENT NO. 09, 35, 51 (DRN 02-216)TABLE 4.11-2 (Continued, See note below) (DRN 02-216)TABLE NOTATIONSa.The LLD, as defined in the ODCM, values for the following types ofanalysis are:Type of AnalysisLLD (µCi/cc)Noble Gas Gamma Emitters1E-04H-31E-06 I-1311E-12 I-1331E-10 Particulate Gamma Emitters1E-11 Gross Alpha1E-11 Sr-89, Sr-901E-11 Gross Beta or Gamma Noble Gas Monitor1E-06b.The principal gamma emitters for which the LLD Requirement applies include the followingradionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases, and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, I-133, Cs-134, Cs-137, Ce-141, and Ce-144 in Iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.c.Samples shall be changed at least once per seven days and analyses shall be completedwithin 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 fromsampler, except for the gross alpha analysis. The gross alpha analysis shall be completedwithin 10 days after changing, or removal from sampler.
The ratio of the sample flow rate to the sampled stream (effluent stream) flow shall be known for the time period covered by each dose or dose rate calculation.d.If no primary to secondary leakage exists, then only the gross beta or gamma analysis(installed radiation monitors) needs to be performed for the Main Condenser Evacuation and Turbine Gland Sealing System (MCES). Sampling and analysis shall be performed when a primary to secondary leak exists.e.Fuel Handling Building sampling is required whenever irradiated fuel is in the storage pool.
f.Tritium grab samples for the Plant Stack 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 /> ifpurging containment with the refueling cavity flooded. (DRN 02-216)NOTE: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO)in accordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-24AMENDMENT NO. 02, 09, 35, 51 (DRN 02-216)TABLE 4.11-2 (Continued, See note below) (DRN 02-216)TABLE NOTATIONg.Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, or aTHERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hourperiod. Analysis for radionuclides 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 sampling. Thissampling is not applicable if the noble gas monitor shows that effluent activity has not increased by a factor of 3. This sampling is not applicable to the MCES WRGM if no primary to secondary leakage exists.h.Samples shall be changed 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 leastseven days following each shutdown, startup, or THERMAL POWER change exceeding15% of RATED THERMAL POWER in 1-hour, and analyses shall be completed within 48hours 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 correspondingLLDs may be increased by a factor of 10. This requirement applies if:
- 1) Primary Coolant Dose Equivalent Iodine-131 concentration has increased by more thana factor of 3; AND2) The noble gas monitor shows that effluent activity has increased by more than a factorof 3.i.Sampling and analysis are required prior to each purge. Sampling andanalysis will be required monthly if purge exceeds 30 days. (DRN 02-216)Note: TRM Table 4.11-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014.Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO) inaccordance with Technical Specification 6.14. (DRN 02-216) 3/4 11-25 AMENDMENT NO. 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION
3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond
the SITE BOUNDARY (see TS Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to:
i) 5 mrad for gamma radiation, and ii) 10 mrad for beta radiation
and,
- b. During any calendar year: Less than or equal to:
i) 10 mrad for gamma radiation, and ii) 20 mrad for beta radiation.
APPLICABILITY
- At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of
the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical
Specification 6.9.2, a Special Report. This Special Report shall identify the cause(s) for exceeding
the limit(s) and define the corrective actions that have been taken to reduce the releases and the
proposed corrective actions to be taken to assure that subsequent releases will be in compliance
with the above limits.
(DRN 04-1191, Am. 91)
The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year
for noble gases shall be determined in accordance with the methodology and parameters in the
ODCM at least once per 31 days.
NOTE: TRM Specification 3.11.2.2 is part of the Offsite Dose Calculation Manual (ODCM),
reference UNT-005-014. Revision of this TRM Specification requires the approval of the General
Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216)
3/4 11-26 AMENDMENT NO. 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.2 GASEOUS EFFLUENTS
DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM
LIMITING CONDITION FOR OPERATION
3.11.2.3 The dose to MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous
effluents released to areas at and beyond the SITE BOUNDARY (see TS Figure 5.1-3)
shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY
- At all times
ACTION: With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous
effluents exceeding any of the above limits, prepare and submit to the Commission
within 30 days, pursuant to Technical Specification 6.9.2, a Special Report. This Special
Report shall identify the cause(s) for exceeding the limit and define the corrective actions
that have been taken to reduce the releases and the proposed corrective actions to be
taken to assure that subsequent releases will be in compliance with the above limits.
(DRN 04-1191, Am. 91)
The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
SURVEILLANCE REQUIREMENTS:
4.11.2.3 Cumulative dose contributions for the current calendar quarter and current
calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form
with half-lives greater than 8 days shall be determined in accordance with the
methodology and parameters in the ODCM at least once per 31 days.
NOTE: TRM Specification 3.11.2.3 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM specification requires the
approval of the General Manager Plant Operations (GMPO) in accordance with
Technical Specification 6.14. (DRN 02-216)
3/4 11-27 AMENDMENT NO. 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.2 GASEOUS EFFLUENTS
GASEOUS RADWASTE TREATMENT
LIMITING CONDITION FOR OPERATION
3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS
HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall
be used to reduce releases of radioactivity when the projected doses in 31 days due to
gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see TS Figure
5.1-3) would exceed either:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY
- At all times.
ACTION:
With radioactive gaseous waste being discharged without treatment and in excess of the
above limits, prepare and submit to the Commission within 30 days, pursuant to
Technical Specification 6.9.2, a Special Report. This Special Report shall include the
following information:
- a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
- c. Summary description of action(s) taken to prevent a recurrence.
(DRN 04-1191, Am. 91)
- d. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
NOTE: TRM Specification 3.11.2.4 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM specification requires the
approval of the General Manager Plant Operations (GMPO) in accordance with
Technical Specification 6.14. (DRN 02-216)
3/4 11-28AMENDMENT NO. 513/4.11 RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS (Continued) 4.11.2.4.1 Doses due to gaseous releases to areas at and beyond the SITEBOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.4.11.2.4.2 The installed Gaseous Radwaste Treatment System shall be demonstratedoperable by meeting Requirements 3.11.2.1, 3.11.2.2 and 3.11.2.3.
3/4 11-29 AMENDMENT NO. 51 , 91 3/4.11 RADIOACTIVE EFFLUENTS
3/4.11.3 SOLID RADIOACTIVE WASTE
LIMITING CONDITION FOR OPERATION
3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with the
process control program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
APPLICABILITY
- At all times.
ACTION:
- a. With solidification or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the
inadequately processed wastes and correct the process control program, the procedures, and/or the solid waste system as necessary to prevent
recurrence.
- b. With solidification or dewatering not performed in accordance with the process control program, test the improperly
processed waste in each container to ensure that it meets burial ground
and shipping requirements and perform appropriate corrective action if
required.
(DRN 04-1191, Am. 91)
- c. The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
SURVEILLANCE REQUIREMENTS 4.11.3 Solidification of at least one representative test specimen from at least every
tenth batch of each type of wet radioactive wastes, (e.g., filter sludges, spent resins),
SHALL BE VERIFIED IN ACCORDANCE WITH THE VENDORS PROCESS CONTROL
PROGRAM.
4.11.3.1 If the initial test specimen from a batch of waste fails to verify solidification, the
process control program shall provide for the collection and testing of representative test
specimens from each consecutive batch of the same type of wet waste until at least
three consecutive initial test specimens demonstrate solidification. The process control
program may be modified if practical to assure solidification of subsequent batches of
waste.
4.11.3.2 If any test specimen fails to verify solidification, the solidification of the batch
under test shall be suspended until such time as additional test specimens can be
obtained, alternative solidification parameters can be determined in accordance with the
vendors process control program, and a subsequent test verifies solidification.
Solidification of the batch may then be resumed using the alternative solidification
parameters determined by the process control program.
3/4 11-30 AMENDMENT NO. 02 , 51 , 91 (DRN 02-216) 3/4.11 RADIOACTIVE EFFLUENTS (See note below)
(DRN 02-216) 3/4.11.4 TOTAL DOSE
LIMITING CONDITION FOR OPERATION
3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER
OF THE PUBLIC due to release of radioactivity and to direct radiation
from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the
total body or any organ, except the thyroid, which shall be limited to less than or equal to
75 mrem.
APPLICABILITY
- At all times.
ACTION:
With the calculated doses from the release of radioactive materials in liquid or gaseous
effluents exceeding twice the limits of Requirement 3.11.1.2.a 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a or 3.11.2.3.b, calculations shall be made including direct radiation
contributions from the reactor units and from outside storage tanks to determine whether
the above limits of Requirement 3.11.4 have been exceeded. This evaluation should be
done in accordance with guidance in the ODCM. If such is the case, prepare and submit
to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special
Report. This Special Report shall define corrective action to be taken to reduce
subsequent releases to prevent recurrence of exceeding the above limits and includes
the schedule for achieving conformance with the above limits. As defined in
10CFR20.2203(a)(4), the Special Report shall include an analysis that estimates the
radiation exposure (dose to a MEMBER OF THE PUBLIC) from uranium fuel cycle
sources, including all effluent pathways and direct radiation, for the calendar year that
includes the release(s) covered by this report. The Special Report shall describe levels
of radiation and concentrations of radioactive material involved, and the cause of the
exposure levels or concentrations. If the estimated dose(s) exceeds the Requirement
3.11.4 limits, and if the release condition resulting in violation of 40 CFR Part 190 has
not already been corrected, the Special Report shall include a request for a variance in
accordance with the provisions of 40 CFR Part 190. Submittal of the report is
considered a timely request, and a variance is granted until staff action on the request is
complete.
(DRN 04-1191, Am. 91)
The provisions of TRM LCO 3.0.3 and 3.0.4 are not applicable. (DRN 04-1191, Am. 91)
NOTE: TRM Specification 3.11.4 is part of the Offsite Dose Calculation Manual (ODCM),
reference UNT-005-014. Revision of this TRM Specification requires the approval of the
General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14. (DRN 02-216)
3/4 11-31AMENDMENT NO. 513/4.11 RADIOACTIVE EFFLUENTSSURVEILLANCE REQUIREMENTS (Continued) 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall bedetermined in accordance with Requirement 4.11.1.2, 4.11.2.2 and 4.11.2.3 and in accordance with the methodology and parameters in the ODCM.4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units andfrom radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Requirement 3.11.4.