ML20195J492
| ML20195J492 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/10/1988 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20195J459 | List: |
| References | |
| NUDOCS 8806290142 | |
| Download: ML20195J492 (13) | |
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. ATTACHMENT II Technical Specification Pages-Affected by Proposed Amendment No.167-PAGES 4-69 1
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. 8806290142 880610 DR.ADOCK 05000312
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21 LIQUID EFFLUENTS 4.21.1 Concentration Surveillance Reauirements The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.15-1.
The liquid effluent continuous monitor having provisions for automatic termination of liquid releases, as listed in Table 3.15-1, shall be used to limit the concentration of radioactive material released at any time from the site to areas beyond the site boundary to the limits given in Specification 3.17.1.
The radioactivity concentration of each Retention Basin to be discharged shall I
be determined prior to release by sampling and analysis in accordance with Table 4.21-1. Item A.
The results of pre-release analyses shall be used with I
the calculational methods in the OFFSITE DOSE CALCULATION MANUAL (00CM) to assure that the concentration at the point of release is within the limits of I
Specification 3.17.1.
Blift1 This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the site boundary for liquid effluent will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within the limits of 10 CFR Part 20.106 to MEMBER (S) 0F THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
There are no continuous releases of radioactive material in liquid effluents from the plant.
All radioactive liquid effluent releases from the plant are by batch method.
s Proposed Amendment No. 53, 98, 167 4-69
a RANCHO SECO UNIT 1 TECHNICAL SPECIFICATTONS Surveillance Standards 4.21.2 Q0111 Dose Calculations Cumulative dose contributions and cumulative dose projections associated with the release of liquid radioactive effluents from the site (see Figure 5.1-3) shall be determined in accordance with the sampling and analyses specified in Table 4.21-1, Item B and the methodology described in the OOCH at the following frequencies:
a.
Prior to the initiation of a release of liquid radioactive effluents from an RHUT, a dose calculation update shall be made; and, b.
Monthly, based on composite analyses of 11guld radioactive effluents released from the A and B RHUTs during a calendar month.
A dose tracking system and administrative dose limits shall be established and maintained. Operating parameters shall be adjusted in accordance with methodology described in the OOCH such that the dose values at any time, when projected to the end of the applicable time period, do not exceed the doses specified in Technical Specification 3.17.2.
HA111 This specification is provided to implement the requirements of Sections II.A. III.A, and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.
Specification 4.21.2 provides the required operating flexibility and, at the same time, implements the guides set forth in Section IV.A of Appendix I which assures, by definition, that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations methodology in the ODCM implements the requirements in Section III.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 Proposed Amendment No. 53, 98, 167 4-70
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCH 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 Dose to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1. October 1977, and Regulatory Guide 1.13. "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
The results from composite samples during the period 1981 through 1984 indicate that Cs-137, Cs-134, Co-58 and Co-60 constitute 80 percent of the historical mix of gamma emitting radionuclides in plant liquid effluents.
Another 13 percent consists of I-131. When the thyroid is separated as a lirciting organ, 97.8 percent of the total body dose and 97.6 percent of the limiting organ dose are due to Cs-134 and Cs-137.
Essentially 100 percent of the tnyroid dose is due to I-131.
The activity analysis of Cs-134. Cs-137 and I-131 at the Lower Limits of Detection specified in Table 4.21-1. Item B for an RHUT sample is based on l
an estirr.ated annual plant radioactive effluent outflow of 20 million gallons per year with a minimum average dilution flow rate of 8,500 gallons per minute. These Lower Limits of Detection equate to an offsite dose commitment of approximately 50 percent of the guidelines specified in 10 CFR 50, Appendh I and provide an adequate basis for determining the presence or i
absence of dose due to other radionuclides in plant liquid effluents, when no other indications are revealed during sample analysis.
The Lower Limits l
of Detection specified in Table 4.21-1, Item B for a composite sample analysis equate to an offsite dose commitment of approximately 10 percent of the 10 CFR 50, Appendix I guidelines.
l The dose tracking system ensures that the dose limits prescribed in Technical Specification 3.17.2 will not be exceeded at the 95 percent confidence level.
The methodology presented in the ODCH provides for adustment of operational l
and analysis parameters to factor in variables such as annual radiological l
liquid effluent release volume, discharge canal flow rate, and current ccmulative dose.
The dose tracking system provides for prompt updating of cumulative dose and contains feedback mechanisms to assure that the 10 CFR 50, Appendix I design objectives are not exceeded.
There is also reasonable assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirement of 40 CFR 141.
Proposed Amendment No. 53, 98, 167 4-71
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit Liquid Release Frequency Frequency Analysis Of Detection Type (LLD)
(uCi/ml)(a)
A. Retention Each Batch Each Batch Principal 3E-7 Basin N/S (b)
P P
Gamma Emitt}a>
qg Nuclides t Dissolved and Entrained Noble Gases 1E-5 (Gama Emitters)
H-3 B. Regenerant Each Batch Each Batch Principal Hold-Up Tank P
P Gamma Emitting 2E-8 A/B (c)
Nuclides (d)
I-131 6E-8 Mo-99, Ba-140 3E-7 Ce-144 lE-7 H-3 1E-5 fichDatch Composite (e)
Principal P
M Gamma Emitting 4E-9 Nuclides (a)
Mo-99 4E-7 Cs-136 6E-9 Sr-89, Sr-90 3E-8 Gross Alpha IE-7 H-3 IE-5 l
l Proposed Amendment No. 98, 167 4-72
{
l
i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 (Continued)
RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.
(1) The lower limit of detection (LLD) for a radionuclide presented in this table is the smallest concentration, expressed in microcuries per milliliter, which is required to be detected, if r' at t, in order to achieve compliance with the limits of Specification 3.17.2 (10 CFR 50, Appendix I) for an RHUT transfer to a Retention Basin or Specification 3.17.1 (10 CFR 20, Appendix B. Table II, Column 2) for a Retention Basin discharge.
(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false pc,sitive and of a false negative determina-tion is stated.
The probabilities of the false positive and false negative are taken as equal at 0.05.
The general equation for estimating the maximum LLO in microcuries per milliliter is given by the following:
LLD - 2.71/t + 3.29S 3.70E4fYEV)exp(-Atc) where 2.71 - factor to account fer Poisson statistics at very low background count rates, and 3.29 - two times the constant used to establish the one sided 0.95 corfidence interval.
Sb - the standard deviation of the background counting rate
- (R /ts + R /t )0.5; where b
b b Rb - background counting rate (counts /second) tb - background counting interval (seconds) ts - sample counting interval (seconds)
Proposed Amendment No. 98, 167 4-72a
i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 (Continued)
BA_Q10 ACTIVE LIOUID MASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of the radiochemical process, i.e., the product of all factors such as abundance, chemical yield, etc.
E = counting efficiency (counts / disintegration)
V - sample volume (milliliters)
X - the radloactive decay gonstant for the particular radionuclide (seconds-1) te - tha elapsed time from midpoint of sample collection to start of counting (seconds)
(3) The LLD is defined as an a pricri (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(4) Occasional 1l/. the presence of interfering nuclides may result in the calculated a posteriori Minimum Detectable Concentration (MDC) excecdin the a priori LLD value.
In such cases, the contribut'ing factors will be identified and documented.
HDC is r.alcult.tv9 using the LLD equation, replacing the a priori parameter values with the a posteriori values, and reducing the 3.29 factor to 1.65.
1.65 is the constant used to establish the one sided 0.95 confidence interval.
Proposed Amendment No. 98, 167 4-72b
A RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Survelliance Standards Table 4.21-1 (Continued)
RADI0ACilyE_Lle)UID WASTE SAMPLING AND ANALYSIS PROGRAM b.
A batch "$ lease it the discharge of liquid wastes of discrete volunc from the north or south Retention Basin.
The Retention Basins are the maximum permissible concentration accountability points for 10 CFR 20 Appendix 9 compliance.
c.
An RHUT will he isolated and its contents thoroughly mixed to assur.
representative sampling prior to transftrring the contents to a Retention Basin. The A and B RHUTs are the dose equivalent accountability pciints for 10 CFR 50, Appendix I compliance, d.
The principal gamma eaitting nuclides included as a minimum in a sample analysis for each sample type are as follows:
Retention Basin RHUT Batch RHUT Comoosit?
Mn-54 Hn-54 Hn-54 Fe-59 Fe-59 Fe-59 Co-58 Co-58 Co-58 Co-60 Co 60 Co-60 Zn-65 Zn-65 Zn-65 Ho-99 Cs.134 Cs-134 T-131 C4-136 Cs-137 Cs-134 Cs-137 Ce-141 Cs-136 Ce-141 Ce-144 Cs-137 Ba-140 Ce-141 Ce-144 Ba-140 All peeks which are measurable and identifiable shall be reported and included in 00Ch evaluations. Nuclidas which are not observed in the analysis shall be reported as "less than" the nuclide's calculated HDC (even if HDC > LLD) and shall not be reported as being present.
The "less than" resui.ts thall be considared "zero" for the purposes of DOCH evaluations, e.
A comptsite sample shall be obtained by mixing liquid aliquot volumes in proportion to the voluae of liquid released from each RHUT.
Propoced Ar,endment No. 98, 167 4-72c
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued)
RADI0 ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.
(1) The lower limit of detection (LLD) for a radionuclide presented in this table is the smallest concentration, expressed in microcuries per unit volume, which is required to be detected, if present, in order to achieve compliance with the limits of Specifications 3.18.1, 3.18.2 and 3.18.3.
(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determina-tion is stated.
The probabilities of the false positive and false negative are taken as equal at 0.05.
The general equation for estimating the maximum LLD in microcuries per cubic centimeter is gi'.en by the following:
LLD - 2.71/ts + 3.29Sh 3.70E4(YEV)exp(-Atc) where 2.71 - factor to account for Poisson statistics at very low background count rates, and 3.29 - two times the constant used to establish the one sided 0.95 confidence interval.
Sb - the standard deviation of the background counting rate
- (R /ts + R /t )0.5; where b
b b Rb - background counting rate (counts /second) tb - backgroerd counting interval (seconds) ts - sample counting interval (seconds) l Proposed Amendment No. 53, 98, 167 4-76
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1.(Continued)
BfDI0 ACTIVE GASE0US HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of the radiochemical process, i.e., the product of all factors such as abundance, chemical yield, etc.
E - counting efficiency (counts / disintegration)
V - sample volume (cubic centimeters)
X=theradioactivedecaycgnstantfortheparticular radionuclide (seconds - )
tc - the elapsed time from midpoint of sample collection to start of counting (seconds)
(3) The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(4) Occasionally, the presence of interfering nuclides may result in the calculated a posteriori Minimum Detectable Concentration (MDC) exceeding the a priori LLD value.
In such cases, the contributing factors will be identified and documented.
MDC is calculated using the LLD equation, replacing the a priori parame'er values with the a posteriori values, and reducing the 3.29 factor to 1.65.
1.65 is the constant used to establish the one sided 0.95 confidence interval, b.
Analysis shall also be performed when gross beta or gamma activity analysis of reactor coolant indicates greater than 10 pCi/ml.
The analysis shall be repeated after each additional increase of 10 pCi/mi in the reactor coolant gross beta cr gamma activity analysis.
l Tritium grab samples shall be taken at least once per seven days from the ventilation exhaust from the auxiliary building stack during refueling and anytime fuel is in the spent fuel pool and the pool temperature exceeds 110*F.
Below 110*F there is essentially no evaporatica from this source.
Proposed An.s _wnt No. 98,167 4-76a j
(
4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued)
RADI0 ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation d.
Samples shall be changed at least weekly 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 />.
Sampling and analysis shall also be performed when reactor coolant indicates 10 pCi/ml gross beta gamma activity and every 10 pC1/mi increases thereafter. When samples collected for less than 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.
Tritium grab samples shall be taken at least daily during refueling e.
activities.
l f.
rrincipal gamma emitters for which the LLD applies are: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous samples and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Ho-99 (or Tc99m), Cs-134, Cs-137, Ce-141, and Ce-144 for particulate samples.
This list does not mean only these nuclides will be detected and reported. Other peaks that are measurable and identifiable shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.2.3.
Nuclides which are not observed for the analysis shall be reported as "less than" the nuclide's calculated HDC (even if HDC > LLD) and shall not be reported as being present.
The "less than" results shall be considered "zero" for the ODCH evaluations. All peaks which are measurable and identifiable shall be reported and entered into the ODCH evaluations.
g.
A gross beta analysis is performed on a monthly basis for each environmental release particulate sample.
If any one of these samples indicates greater than 1.0 E-11 pCi/cc gross beta activity, then a Sr-89 and Sr-90 analysis will be performed on those samples exceeding l
this value.
h.
A gross alpha analysis is performed on a monthly basis for each l
environmental release particulate sample.
This fulfills the requirements of performing a monthly composite.
i.
After purging seven reactor building volumes, a technical evaluation, i
prior to reinitiation of a purge following an out of service period, may be conducted in lieu of sampling and analysis.
Proposed Amendment No. 53, 98, 167 4-76b
3 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)
HAXIMUH VALUES FOR THE LOHER LIMITS OF DETECTION (LLD)a, d Table Notation a.
(1) The lower limit of detection (LLD) for a radionuclide presented in this table is the smallest concentration, expressed in picocuries per unit sample, which is required to be detected, if present, in order to achieve compliance with the applicable regulation, given stated operating conditions and calculation methodology.
(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determina-tion is stated. The probabilities of the false positive and false negative are taken as equal at 0.05.
The general equation for estimating the'maxii.1um LLD in picocuries per unit sample is given by the following:
LLD - 2.71/ts + 3.29Sb 3.7E-2(YEV)exp(-Xtc) where 2.71 - factor to account for Poisson statistics at very low background count rates, and 3.29 - two times the constant used to establish the one sided 0.95 confidence interval.
1 Sb - the standard deviation of the background counting rate
- (R /ts + R /t )0.5; where b
h h Rb - background counting rate (counts /second) tb - background counting interval (seconds) ts - sample counting interval (seconds) l l-l l
i l
Proposed Amendment i:c. 53, 98, 167 l
4-85 i
I
F:
Y RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)
MAXIMUM VALUES FOR THE LOHER LIMITS OF DETECTION (LLD)a, d Table Notation 3.7E disintegrations /second/ picocurie l
Y - yield of the radiochemical process, i.e., the product of all factors such as abundance, chemical yield, etc.
F - counting efficiency (counts / disintegration)
V - sample volume (liters) or mass (kilograms)
A - the radioactive decay constant for the particular radionuclide (seconds-l) te - the elapsed time from midpoint of sample collection to start of counting (seconds)
(3) The LLD is defined as an a. priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(4) Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may result in the a posteriori minimum detectable concentration value exceeding the a priori LLD value.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
Proposed Amendment No. 53, 87, 98, 167 4-85a
.,