ML19317G716
| ML19317G716 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/12/1978 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19317G713 | List: |
| References | |
| NUDOCS 8003270692 | |
| Download: ML19317G716 (6) | |
Text
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.s h-of each unit.
Meteorological calculations for offsite locations were performed, and the most critical one was selected to set the release rate.
The controlling distance is 640 meters to the north.
The gamma dose contribution was -determined using the equation 7 63 in Section 7-5.2.5 of Meteorology and Acomic Energy -
releases from vents are considered to be ground level releases which 1968 The could result in a beta dose from cloud submersion.
The beta dose Section 7-4.1 of _ Meteorology and Atomic Energy - 1968. contr dose contribution was determined on the basis of an infinite cloud The beta
_ passage with semi-infinite geometry for a ground level release
( submersion dose).
The beta and gamma components of the gross radioactivity in gaseous effluents were combined to determine the
~ llowable continuous release rate.
a a continuous release rate of gross radioactivity in the amountBased on these calc specified in 2.6.3.A(1) will not result in offsite annual doses above background in excess of the limits specified in 10 CFR Part 20.
The average gamma and beta energy per disintegration used in the equation of Specification 2.6.3.A(1) will be based on the average composition of gases determined from the pla'nt vent and ventilation exhaus ts.
The average energy per beta or gamma disintegration for those radioisotopes determined to be present from the isotopic analyses are given in Table 2.6-3.
tutere isotopes are identified that are not listed in Table 2.6-3, the gamma energy are determin d from Table of Isotopes, C. M. Lederer, J. M. Hollander, and I e
Sixth Edition,1967, and the beta energy shall be as given in USNRDL TR 802
. Perlman, II.
P. E. Zigman, and J. L. bbckin. Spectra of Individual Negatron Emitters _ (Beta Sp For Specification 2.6.3. A(2), dose calculations have been made for the critical sectors and critical pathways for all radiciodi and radioactive material in particulate form, which half-lives nes greater-than eight days.
-for these: releases.
The calculations consider site peteorology For radioiodines and radioactive materials in particulate form controlling sector for unit vent releases is the N sector at a
, the distance of 640. meters (X/Q = 7.8 x 10-6 3
sec/m ) for the dose due to inhalation.
The nearest milk cow is _ located in the NW sector at a distance of 11,000 meters.
milk' cow is 7.05 x 10-8 sec/m.The applicable X/Q at the nearest 3
chain is controlling.
The grass-cow-milk-child thyroid The assumptions used for these calculations are:
(1) onsite meteoro-logical data for the most critical 22.5 degree sector; building wake; and '(3) a reconcentration factor 243 was applied for (2) credit for possible ecological chain effects from radioactive iodine and particulate releases.
8003 270 hh
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Specification 2.6.3.B establishes upper limits for the releases of noble gases, iodines and.particulates with half-lives greater than eight days,'and iodine-131 at twice the design objective annual quantity during any calendar quarter, or four times the design
. objective annual quantity during any period of 12 consecutive months.
The intent of.this specification is to permit the licensee the flexibility of. operation to assure that the public is provided a dependable source 'of power 'under unusual operating conditions which may temporarily result in higher releases than the objectives.
In addition to the limiting conditions for operation of' Specifications 2.6.3.A and 2.6.3.B, the reporting requirements of 2.6.3.C delineate that the cause be identified whenever the release of gaseous effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such release rates to the design objectives.
Specification 2.6.3.D requires that suitable equipment to monitor and control the radioactive gaseous releases are operating during any period these releases are taking place.
Specification 2.6.3.E limits the maximum offsite dose above background to below the limits of 10 CFR Part 20, postulating that the rupture of a waste gas storage tank holding the maximum activity releases all of the contents to the atmosphere.
The sampling and monitoring requirements given under Specification 2.6.4 provide' assurance that radioactive materials released in gaseous wastes are properly controlled and monitored in conformance with the. requirements of Design Criteria 60 and 64.
These require-ments provide the data for the licensee and the Commission to evaluate the plant's perfor. nance relative to radioactive wastes released to the environment.
Reports on.the quantities of radioactive materials re-leased'in gaseous effluents are furnished to the Commission on the basis of Section 5.6.1 of these Technical Specifications and in conformance with Regulatory Guide.l.21.
On the basis of such reports and any
- additional information the Commission may obtain from the Jicensee orlothers, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
Section 2.6.4 identifies the environmental release points for gaseous radioactivity, and sets forth monitoring and -sampling requirements for these
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points. The condenser air ejector and the turbine gland _ seal exhaust are not included-infthejlist of' release points because their exhausts are routed t 56 the auxiliary building stack, where they are monitored and sampled. A requirement for monitoring the gaseous radioactivity 'of these two streams is included to provide the capability -for detection of radioactivity in the
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secondary system. which would ' indicate leakage in the steam generators. -
i-Proposed Amendment No. 56.
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. Specification 2.6.4'.B excludes monitoring the turbine build.ng venti-
'lation exhaust since this rel' ease.is expected to be a negligible release' point. Many PWR reactors do not have turbine building
, enclosures. To be consistent in this requirement for all PWE reactors, :the monitoring of gaseous releases from turbine buildings is not required.
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. 2. 6 '. 5 L - Specifications ~for Solid Waste Handling and Disposal A.
Measurements shall be made to determine. orfestimate the total curie quantity and principle isotopic composition of all radio-active solid waste shipped offsite.
B.
Solid wastes in storage and preparatory to shipment shall be monitored and packaged to awsure compliance with 10 CFR Part 20 10'CFR Part 71, and 49 CFR Parts 171-178.
C.
Reports.of the-radioactive solid waste shipments, volumes, principle isotopes, and total curie quantity, shall be submitted in accordance with Section 5.6.1.
- Bases The requirements for solid radioactive waste' handling and disposal given under Specification 2.6.5 provide assurance that solid radio-active materials stored at the plant and shipped offsite are packaged
. in conformance with 10'CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.
These requirements provide the data for the licensee and1the l
Cotatission to evaluate the handling and storage facilities for solid radwaste, and to' evaluate the environmental impact of offsite shipment and' storage. -Reports on.the quantities, principle isotopes and
- volumes ;of the shipments, are furnished to the Commission according to Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission ray from time to time require the licensee to take such action as the Commission deems appropriate.
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Table 2.6-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous' Sampling Type of 5,
qhle-Source
' Frequency Activity. Analysis Con a;;.
(pC1/ml) gons
-Waste Cas' Decay ~
Each Tank Individual Camma Emitters 10 4-(2)
Tank Releases 11 10 6
-Containment Purge Releases Each Purge Individual Camma Emitters 10 4-(2)'
11 - 3 10
- Radwaste ' Service Area Fan EF-A-9 Monthly Individual Camma Emitters
'10-(
(
II-3 10-6 Auxiliary-Building Stack Monthly Individual Camma Emitters 10-4 (2)(3)
. Reactor Building Stack (Gas Samples) 11 - 3 10-6 h
Weekly (Charcoal Sample) 1-131 10-12 (4)
. Monthly ~(Charcoal Sample)
I-133, I-135 10-10 Weekly (Particulates)
Individual Gamma Emitters (at least for Ba-La-140, I-131 10-11 (4)~
Monthly Composite S r-89 10-11 (PartIculates)
Gross a 10-I1
-1 Quarterly. Composite S r-90 10 (Particulates)
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