ML19325F027
| ML19325F027 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/26/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325F023 | List: |
| References | |
| NUDOCS 8911130239 | |
| Download: ML19325F027 (17) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
f W ASHING TON, D. C. 20068 SACRAMENTO MUNICIPAL UTILITY Di$TRICT DOCKET NO. 50-312 RANCH 0 SECO NUCLEAR GENERATING STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendsent No.114 License No. DPR-54
'l 1.
The Nuclear Regulatory Courission (the Cosmission) has found that:
A.
The application for amendment by Sacramento Municipal Utility District (the licensee) dated June 10,1988 as revised January 11, 1989 complies with the standards and requirements asamended(theAct),and of the Atomic Energy Act of 1964,forth in 10 CFR Chapter I; the Commission's regulations set B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; There is reasonable assurance (1) that the activities authorized C.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the conson defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicabic requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications 4s indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby j
amended to r9ad as follows:
(2)TechnicalSpecifications j
i The Technical Specifications contained in Appendices A and B, as revised through Asendment No.114, are hereby incorporated in the licerse. The licensee shall operate the facility in accordance with the Technical Specificationa.
j 3.
This license amendment shall become effective within 30 days of the issuance date.
The implementation delay is provided to allow time for l
modification of affected procedures and promulgation of the changes to i
personnel.
FOR THE NUCLEAR REGULATORY COMMISSION l
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eorge Knighton irector Project irectorat V Division of Reactor Projects !!!,
IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of 1ssuance: October 26, 1989 I
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1 ATTACHMENT TO LICENSE AMENDMENT,WO.114 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50 312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert vi vi X
X 4-69 4-69 4-70 4-70 4-71 4-71 4-714 4-71b 4-72 4-72 4-72a 4-72a 4-72b 4-72b 4-72c 4-72c 4-72d 4-72e 4-76 4 76 4-76a 4-76a 4-76b 4-76b 4-85 4-85 4-25s 4-85a l
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e 4ANCWO $[C0 UNIT 1 TECNNICAL SPECIFICATIONS TABLE OF CONT [NTS (Continued) 181114A 2181 l
4.11 REAETot SUILBf WC PURSE EXWAUST FILTERINC SYtttM 4 43 j
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4,12 AUYf L1 ARY AND iPtWT Futt Ruf LBf WS FILTtt SY1TtWt 4 43 4.13 AUCWINTtB "NittFct fWGPtCTION Ptofit&W Fat NICW 4 44
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thttGY LIN :1 Ou"SIBt 0 F cohTaikuth "
4.14
$NVBBER$
4 47 i
4.18 RADIDACTIVE MAftt! Att 10Uttti 4 48 4.16 Reserved 4-49 l
4.17 17t4N CtN[tAfott 4.g)
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l 4.17,1 Steam Gemeenter ta*nie telection and Innssetten
,4 51 4.17.2 tteam Generater Tube taania telection and Innesetten 4 5) 4.17.3 Inaneetten Freaueneisa 4 53 l
4.17.4
- Definitions 4 54 l
4.17.8 14ang11 4 54 f
t 4.17.8 OTSG Availlary Feedveter Needer Surveillance 4 55 j
4.17.7 Inspection Acceptance Criteria and Corrective Actions 4 55 i
4.17.8 Report 4 55 I
4.18 FItt SUPPPt1110N SY1TfM RURVI!LLAMCI 4 58 i
l 4.19 RADICACTIVE L10UID EFFLUENT MONITORING INSTRUNENTATION 4-63 4.20 RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-65 i
4.21 L10UID EFFLUENTS 4 69 l
4.21.1 concentration 4-69 4.21.2 Q2111 4-72
,l 4.21.3 Lieuid Holdue Tankt 4-13 4.21,4 Liouid Effluent Radwaste Treatment 4-734 l
e.en No.,,.,,....,. u. u 6. m
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RANCHO SECO UNIT 1 I
TECHNICAL SPECIFICATIONS j
LIST OF TABLES j
Ishlt tant 4.1 2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 M!N! MUM SAMPLING FREQUENCY 4-9 4.6-1 D!!$EL GENERATOR TEST SCHEDULE 4-34j 4.6-2 ADDITIONAL RELIAh!LITY ACTIONS 4-34k l
4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 l
DURING INSERVICE INSPECTION l
l 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 I
4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-574 f
4.17 3 OTSG AUXILIARY FEEENATER HEATER SURVEILLANCE 4-57b.c 4.17 4 SPECIAL PER!PHERAL GROUP TUBt$
4*S7d g f
4,1 bl SPECIAL LANE REGION GROUP TUBES 4 57h j
4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66
$URVEILLANCE REQUIREMENTS 4.21-1 RADIDACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-70 f
4.22-1 RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYS!$ PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOMER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVE!LLAhCE REQUIREMENTS 4-88 i
4.34-)
METEOROLOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 MINIMUM SHIFT CREN COMPOSITION 6-2 t
Amendment No. 28, 66, 76, 88, 94, 96, 97, 98, 196, 119. 114 x
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21 LIQUID EFFLUENTS
'4.21.1 Coneentration Surveillance Renuirements The concentration of radioactive material at any time in liquid effluent released from the site shall be continuously monitored in accordance with Table 3.15-1.
Th'e liquid effluent continuous monitor having provisions for automatic i
termination of liquid releasts, as listed in Table 3.15-1, shall be used to 1,imit 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 l
be determined prior to release by sampling and analysis in accordance with Table 4.21-1, Item A.
The results of Retention Basin pre-release sample analyses shall be used with the calcu14tional methods described in the OFFSITE DOSE CALCULATION MANUAL (ODCH) to ensure that the concentration at the point of release is within the limits of Specification 3.17.1.
B1111 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 will be less than the concent ation levels specified in 10 CFR l
Part 20 Appendix B, Table II, Column 2 for liquid effluent. 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 HEMBER(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, f
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l Amendment No. 53, 98.114 4-69
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS j
Surveillance Standards i
4.21.2 Q0111 j
Dose Calculations i
Cumulative dose assessments associated with the release of radioactive i
liquid effluent shall be determined by sampling and analysis in accordance l
l with Table 4.21-1 Item B and calculations performed in accordance with the l
l methodology described in the ODCM at the following frequencies:
l a.
Prior to tb9 initiation of a release of radioactive liquid effluent from the A or 8 AHUT; and.
L b.
Upon verification of monthly composite analysis results for radioactive liquid effluent released from the A and B RHUTs.
A dose tracking system and administrative dose limits shall be established and maintained. With the 31-day dose projection in excess of the i
Specification 3.17.4 limits, adjust liquid effluent operating parameters to give reasonable assurance of compliance with the dose lir.its of f
Specification 3.17.2 (10 CFR 50, Appendix I dose guidelines) and mainta'.n radioactive liquid releases as low as is reasonably achievable.
W This specification is provided to implement the requirements of Sections
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II.A. III.A. and IV.A of App ndix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1.
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 calculation methodology in the ODCH implements the requirements in Section
[
III.A of Appendix ! that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the OOCH for calculating the doses due to the actual release rates of radioactive materitis in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dose to Man from Routine i
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 i
and Routine Reactor Releases for the Purpose of Implementing Appendix I,"
April 1977.
l Amendment No. 53, 98,114 4-70
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Tne Lower Limits of Detection established in Table 4.21-1. Item B are based on an estimated maximum annu il effluent outflow of 20 million gallons with a minimum annual average flow rate in the plant effluent stream of t
8,500 gallons per minute. The RHUS -pre-release Lower Limits of Detection l
equate to an offsite dose of less than 50 percent of the 10 CFR 50, Appendix
?
I guidelines. The monthly RHUT composite Lower Limits of Detection equate to an offsite dose of less than 10 percent of the 10 CFR 50 Appendix !
guidelines. These Lower Limits of Detection along with the dose tracking system give reasonable assurance that the dose limits prescribed in Technical Specification 3.17.2 (the 10 CFR 50, Appendix I dose guidelines) will be met.
Tnere is also reasonable assurance that the operation of the facility will
.not result in radionuclide concentrations in finished drinking water that i
are in excess of the requirement of 40 CFR 141.
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Amendment No. 53, 98.114 4-71 7
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,e; RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 RADI0 ACTIVE LIQUID MASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Sampling Minimum Analysis Type of Activity Lower Limit Type Frequency Frequency Analysis of Detegtton (LLD)sa).
(pCi/ml)
Each Batch Each Batch Mn-54, Fe-59 A. Retention (t)
Basin N/S P
P Co-58, Co-60 Zn-65. Mo-99 Cs-134 Cs-136 3E-7 Cs-137, 64.140 Co-141, Co-144 I-131 Dissolved and Entrained Noble Gases IE-5 (Gamma Emitters) l
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H-3 B. Regenerant Each Batch Each Batch Mn-54, Fe-59 Hold-Up Tank P
P Co-58, Co-60 A/B (c.d)
Zn-65, Cs-134 2E-8 Cs-137, Ce-141 1-131 Cs-136 BE-9 Mo-99, Ba-140 i-Ce-144 6E-8 H-3 1E-5 l
Each Batch Composite (8)
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I Zn-65 6E-9 1
1 Fe-59 BE-9 St-89' SE-9
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TECHNICAL SPECIFICATIONS Surveillance Standards
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Table 4.21-1 (Continued)
RADIOACTIVE LIOUID HASTE SAMPLING AND ANALYSIS PROGRAM i
Table Notation a.
(1) The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentrations (expressed in microcuries per milliliter) which are required-to be detected, l
'if present, in order to give reasonable assurance of compliance with the limits of Specification 3.17.2 (10 CFR 50, Appendix I) for an RHUT transfer to a Retention Basin and asturance of r
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compliance with the limits of Specification 3.17.1 (10 CFR 20, Appendix B. Table II, Column 2) for a Retention Basin discharge.
(2) The LLD of a radionnalysis system is that value which will indicate the cresence or absence of radioactivity in a-sample when the probability of a false positive and of a false negative determina-
'tlon is stated. The probabilities of the faltt positive and false negative are taken as equal at 0.05.
The general equation for estimating the maximum LLD in microcuries per milliliter is given by the following:
l LLO -
2.71/t + 3.295b-3.70E4(Y V)exp(-Atc) y 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.
b - the standard deviation of the background counting rate S
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-(B/(tt,)+B/t[)**
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- where, L
B = background counts L
tb - ha.';round counting interval (seconds) 1 p
ts - sample counting interval (seconds) l e
Amendment No. 98,114 4-72a f,
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Surveillance Standards Table 4.21-1 (Continued)
RADI0 ACTIVE LIOUID WASTr SAM'PLING AND ANALYSIS PROGRAM Table Notation
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i 3.70E4 = disintegrations /second/ microcurie Y = yield of the radiochemical process, i.e., the p-oduct of all factors such as abundance, chemical.yleid, etc.
l E = counting efficiency (counts / disintegration)
V = sample volume (milliliters)
A = the radioactive decay 9onstant for the particular radionuclide (seconds-')
te - the elapsed time from midpoint of sample collection to the midpoint 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 (af ter the fact) basis.
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Amendment No. 98,114 4-72b 1.
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h RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 (Continued)
RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation b.
A batch release is the discharge of liquid wastes of discrete volume l
from the north or sourn Retention Basin. The Retention Basins are the maximum permissible concentration accountability points for 10 CFR 20 Appendix B compliance.
c.
An RHUT will be isolated and its contents thoroughly mixed.to assure representative sampling prior to transferring the contents to a i
Retention Basin. The A and B RHUTs are the dose equivalent accountability points for 10 CFR 50, Appendix I compliance, d.
Isotopic peaks which are measurable and identifiable from an RHUT pre-release sample analysis shall be reported and-included in 00CM i
evaluations. Nuclides which are not observed in the analysis shall be 4
I reported as "less than" the nuclide's a posteriori minimum detectable concentration.and shall not be reported as being present. The "less than" results shall be considered "zero" for the purposes of JDCM evaluations; however, if a nuclide is measured and identified at a value less than the Table 6.21-1 LLD value, it shall be reported and entered in ODCM evaluations.
Isotopic peaks verified to be measurable and identifiable from a monthly F4UT composite sample analysis which were not identified on a pre-reletse analysis during the composite period shall be reported and included.,in 00CM evaluations to update the cumulative doses, A composite sample shall be obtained by mixing liquid aliquot volumes e.
in proportion to the volume of liquid released from each RHUT.
11 Amendment No. 98.114 4-72c
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIGdS burveillance Standards Table 4.22-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND AHALYSIS PROGE 6 Table Notation a.
(1) The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentration-(expressed in microcuries per unit volume) which are required to be detecteo, if present, in order to achieve compliance with the limits of i
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 given by the following:
LLD.
2.71/ts + 3.29S __
h 3.70E4(YEV)exp(-Mc) where 2.71 - factor to account for Poisson statistics at very low l
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 o.
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. (B/(t t ) + B/t')***
bs where.
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B = background counts 7
tb = background counting interval (seconds) ts - sample counting interval (seconds) v l
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Amendment No. 53, 98, 114 4-76
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards l
Table 4.22-1 (Continued)
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l RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSJS' PROGRAM
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Table Notation 3.70E4. disintegrations /second/ microcurie Y = yield of the radiochemical process, i.e., the product of all factors such as abundance, chemical yleid, etc.
l E = counting efficiency (counts / disintegration)
V - sample volume (r.ubic centimeters)
A. the radioactive decay cpnstant for the particular radionuclide (seconds -')
t te the elapsed time from midpoint of sample collection to the midpoint 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, b.-
An analysis shall also be performed when a gross beta or gamma activity analysis of reactor ex1 ant indicates greater than 10 pCi/ml. The analysis shall be repeated after each additional increase of 10 pCi/ml in-the reactor coolant gross beta or gamma activity analysis.
I c.
Tritium grab samples shall be taken at~1 east once per seven days from i -
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 evaporation from this source.
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Amendment No. 98,114 4-76a f
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RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PRCGRAM J
Igh]g 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 t
performed when reactor coolant indicates 10 pC1/ml gross beta gamma activity and every 10 pCi/ml 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.
e.
. Tritium grab samples shall be taken at least daily during refueling activities.
P f.
Principal 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 Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99 (or Tc-99m), Cs-134 Cs-137, Cw-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 be reported in the Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.2.3.
All peaks which are measurable and identifiable shall be reported and entered into the 00CM evaluations. Nuclides which are not l
observed for the analysis shall be reported as "less than" the l
nuclide's a posteriori minimum detectable concentration a-d shall not L
be reported as being present. The "less than" results shall be.
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considered "zero" for the ODCM evaluations; however, if a nuclide is L
measured and identified at a value less.than the Table 4.22-1 LLD I
value, it shall be reported and entered in OOCH evaiuations.
g.
~A gross beta analysis is performed on a monthly basis for each environmental release particulate sample. If any one of these samples l
. indicates greater than 1.0 E-11 pCi/cc gross beta activity, then a l
Sr-89 and Sr-90 analysis will be performed on those samples exceeding
+
this value, h.
A gross alpha analysis is performed on a monthly ba:is for each environmental release particulate sample. This fulfills the requirements of performing a monthly composite.
1.
After purging seven reactor building volutes, a technical evaluation, prior to reinitiation of a purge following an out of service period, may be conducted in lieu of sampling and analysis.
Amendment No. 53, 98,114 4-76b p
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-l TECHNICAL SPECIFICATIONS Surveillance Staidards Table 4.26-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a.d Jable Notation a.
(1) The Lower Limits of Detection (LL0s) for the radior.uclides presented in this table are the LLD values recommended in
.NUREG-0472. RJvision 2, and NRC Branch Technical Position dated November 1979 for an acceptable Radiological Environmental Monitoring Program.
(2) The LLD of a radionnalysis 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-1 tion is stated. The probabilities of the false positive and false e
negative are taken as equal at 0.05.
The' general equation for-l estimating the maximum LLD in picocuries per unit sample is given by the following:
LLD =
2.71/t + 3.29Sh 3.7E-2(YkV)exp(-Me) 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
=(B/(tt)+B/t[)*
bs l
where.
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B = background counts I
tb = background counting interval (seconds)
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ts = sample counting interval (seconds) l Amendment No. 53, 98,114 4-85
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a.d Table Notation 3.7E-2 = disintegrations /secondipicoeurie 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 = 1emple volu 9 (liters) or mass (kilograms)
A - the radion 21ve decay onstant for the particular radionuclide (seconds-t) t,; = the elapsed time from midpoint of sample collection to the midpoint 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 tha fact) basis.
(4) Occasionally, unavoidably small sample sizes or other uncontrollable circumstances may result in a priori LLD values not being met.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
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Amendment No. 53, 87, 98,114 4-85a
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