ML19317G766
| ML19317G766 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/07/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G759 | List: |
| References | |
| NUDOCS 8004010593 | |
| Download: ML19317G766 (11) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION j
wAsmucTow. o. c. 20ssi SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 21 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comissica) has found that:
A.
The application for amendment by Sacramerto Municipal Utility District (the licensee) dated April 12, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR ChapterI; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (if) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this 1' cense
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amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 21, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
)
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: August 7, 1978 k
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ATTACHMENT TO LICENSE AMENDMENT h0. 21 FACILITY OPERATING LICENSE NO. DPR-54 i
i DOCKET NO. 50-312 Revise Appendix B as follows:
4 Remove Pages Insert Pages i
15-22 15-22 The changes on the revised pages are shown by marginal lines.
Pages 17, 20 and 21 are unchanged and are included for convenience only.
I 4-a I
I 1
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3 D
I (2)
If the average release rate of all iodines and radioactive gi b
ndterials in particulate form with half-lives greater than l
J ll eight days during any calendar quarter is:
g j
g v
8.55 x 106 31 (3)
If the amount of iodine-131 released during any ' calendar quarter is greater than 0.5 C1.
D.
During the release of gaseous wastes frm the primary system waste gas holdup system, the effluent mon!Mr shall be operating and set te alarm and to initiate the automatic closure of the waste gas dischcege valve prior to exceeding the limits specified in 2.6.3.A (1) above. The operability of the automatic isolation valves shall be demonstrated quarterly.
E.
The maximum activity to be contained in one waste gas storage tank shall not exceed 135,000 curies (considered as Xe-133).
2.6.4 Specifications for caseous Waste Sampliac and Monitoring A.
Plant records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section 5.6.1 of these Specifications.
Esticates of the error associated with each reported value should be included.
B.
Gaseous releases to the environment, except from the turbine building ventilation exhaust and as noted in Specification 2.6.4.C, shall be continuously conitored for gross radioactivity, and the l
flow measured and recorded. These releases originate frem the reactor building stack, from the auxiliary building stack, and from the radwaste service area fan (EF-A-9). Whenever a conitor at one of these release points is inoperable, grab samples shall be taken and analyzed daily for gross radioactivity.
If a conitor is inoperable for more than seven days, releases from that point shall be terminated.
C.
The condenser air ejector and the gland seal exhausts shall be continuously monitored for gaseous radioactivity.
If a monitor
)
is inoperable, grab samples shall be taken and analyzed dai.).y for gascous radioactivity.
D.
During the release of gaseous wastes from the primary system waste gas holdup system, the gross activity monitor, the iodine col-lection device, and the particulate collection device shall be operating.
E.
All waste gas monitors shall be calibrated at least quarterly l
by means of a known radioactive source which' has been calibrated to a National Bureau of Standards source.
Each tonitor shall have a functional test at least monthly dnd instrument check at least daily.
Amendment No. 2,1-
_13._
m F.
Sampling and analysis of radioactive caterial in gaseous waste, particulate form, and radiciodine shall be performed in accordance with Table 2.6-2.
Bases The release of radioactive caterials in gaseous wastes to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20, and in accordance with the requirements of 10 CFR Part 50.36a.
These specifications provide reasonable assurance that the resulting annual air dose due to gs==a radiation will not exceed l'0 mrad, and an annual air dose due to beta radiation will not exceed 20 mrad from noble gases and that the annual dose to any organ of an individual from iodines and particulates will not exceed 15 mrem. At the same time these specifications permit the flexibility of operation, compatible with con-siderations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditious which may te=porarily result in releases higher than the design objective levels but still within the concentration limits specified-in 10 CFR Part 20.
It is expected that using this operational flexibility under unusual operating conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as' practicable, the annual rolesses will not exceed a small f raction of the concentration limits specified in 10 CFR Part 20.
These ef forts should include consideratien of meteorological conditions during releases.
There is a reduction factor of 243 by which the maximum permissible concentration of radioactive iodine in air should be reduced to allow for the grass-cow-milk pathway.
(The factor is 1220 for 1
the grass-goat-milk pathway.) This factor has been derived for radioactive iodine, taking into account the milk pathway.
It has been applied to radionuclides of iodine and to all radionuclides in particulate form with a half-life greater than eight days.
The factor is not appropriate for iodine where milk is not a pathway of exposure or for the other radionuclides.
The design objectives have been developed based on operating experience taking into account a combination of system variables including def ective fuel, primary system leakage, primary to secondary system leakage, and the performance of the various i
waste treatment systems.
For Specification 2.6.3.A(1) dose calculations have been made for the critical sector.
These calculations consider site me*.eorology, buoyancy characteristics, and radionuclide concent of the effluent D
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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 Atomic Energy - 1968.
The releases from vents are considered to be ground level releases which could result in a beta dose from cloud submersion.
The beta dose contribution was determined using Equation 7.21, as described in Section 7-4.1 of Meteorology and Atomic Energy - 1968. The beta dose contribution was determined on -he basis of an infinite cloud 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 allawable continuous release rate.
Based on these calculations, a continuous release rate of gross radioactivity in the amount 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 plant vent and ventilation exhauset.
The avertfe energy per beta or gamma dis 1ntegration for those radioisotopes ds? ermined to be present from the isotopic analyses are given in Tille 2.6-3.
Where isotopes are identified that are not listed in Table 2.6-3, the gamma energy are determined from Table of Isotopes, C. M. Lederer, J. M. Hollander, hnd I. Perlman, Sixth Edition, 1967, and the beta energy shall be as given in USNRDL-TR-802j II.
Spectra of Individual Negatron Emitters (Beta Spectra),
O. Hog.., P. E. Zigman, and J. L. Mackin.
For Specification 2.6.3. A(2), dose calculations have been made for the critical sectors and critical pathways for all radiciodines and radioactive material in particulate form, with half-lives greater than eight days.
The calculations consider site meteorology for these releases.
For radiciodines and radioactive materials in particulate form, the controllingsectorforunitventreleasesistgeNsectorata distance of 640 meters (X/Q = 7.8 x 10~ sec/m ) for the dose due to inhalation.
The nearest milk cow is located in the NW sector at a distance of 11,000 mgters. 3The applicable X/Q at the nearest
- sec/m.
The grass-cow-milk-child thyroid milk cow is 7.05 x 10 chain is controlling.
The assumptions used for these calculations are:
(1) onsite meteoro-logical data for the most critical 22.5 degree sector; (2) credit for building wake; and (3) a reconcentration factor 243 was applied for possible ecological chain effects from radioactite iodine and particulata releases.
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Specification 2.6.3.3 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 tiees 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 of fsite dose above background to below the limits of 10 CFR Part 20, postulating that the rupture of a waste gas storage tank' holding the =aximum activity releases all of the contents to the atmosphere.
The sampling and monitoring requirements given under Specification 2.6.4 provide assurance that radioactive caterials released in gaseous wastes are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64 These r. quire-ments provide the data for the licensee anc the Commission to evaluate the plant's performance relative to radioactive wastes released to the environment. Reports on the quantities of radioactive caterials 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 1.21.
On the basis of such reports and any additional information the Com=ission may obtain from the licensee or others, the Commission may from time to tice require the licensee to take such action as the Commission dee s appropriate.
Section'2.6.4 identifies the environmental release points for gaseous radioactivity, and sets forth monitoring and sampling -requirements for these points. The condenser air ejector and the turbine gland seal exhaust are not included in the list of release points because their exhausts are routed to the auxiliary building 8 tack, where they are conitored and sampled.
A requirement for =onitoring the gaseous radioactivity of these two streams is included to provide the capability for detection of radioactivity in the secondary system, which would indicate leakage in the steam generators.
Amendment No. 2 1 D 0
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4-s Specification - 2.6.4.3 excludes =enitoring the turbine building venti-lation exhaust since this release is expected to be a negligible release point. !bny PWR reactors do not have turbine building enclosures. To be consistent in this require =ent for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required.
2.6.5 Specifications for Solid Waste Handling and Disposal' A.
Heasurements shall be made to determine or estimate 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 assure compliance with 10 CFR Part 20 10 CFR Part 71, and 49 CFR Parts 171-178.
C.
Reports of the radioactive solid waste shipments, volu=es, 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 require = ants provide the data for the licensee and the Com=1ssion to evaluate the handling and storage facilities for solid radwaste, and to evaluate the environmental impact of offsite ship =ent and storage.
Reparts on the quantities, principle isotopes and volunes of the shtpeents, are furnished to the Cc= mission according to Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional infor=ation the Coc=ission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
(m Amendment No. b
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Table 2.6-1
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RADIOACTIVE LIQUID SAMPLING AND ANALYSIS Liquid Sampling Type of Detectable Source Frequency Activity Ax)alysis Concentra ions-(pci/ml) 3)
A.
Tank Batch Releases Each Batch Individunt Camma Emitters 5 x 10-7 (2)
One Batch / Month Dissolved Cases 10-5 Weekly Composite ( )
Ba-La-140, I-131 10-0 e
-8 g
Sr-89 5 x 10 Monthly Composite ( }
-5 H-3 10
-7 Gross 6' 10 Quarterly Composite (l)
Sr-90 5 x 10-8 1
(M E='EJ.M SE) G99
' ce;D N
g EED u-
e Table 2.6-1 (Continued)
NO'iES :
(1)
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
(2)
Fce certain mixtures of ga=ma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations.
Under these circumstancet, it will be more appropriate to calculate the concentrations of such radio-nuclides using measured ratios with those radionuclides which are routinely i(entified and measured.
(3)
The detectability Ibnits for activity analysis are based on the technical feasibility and on the potential significance in the environ =ent of the quantities released.
For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
(4)
The power level and clea*.up or purification flow rate at the sample time shall also be reported.
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Table 2.6-2 RADI0 ACTIVE CASE 0llS WASTE SAMPLING AND ANA13 SIS 9
o Caseous Sampling Type of Detectable N
Source Frequency Activity Analysis Concentrt ons g
(pC1/ml)
A.
Waste Cas Decay Each Tank Indtvidual Camma Emitters 10 /.
(2)
Tank Releases 11 - 3 10 6 B.
Containment Pur^ge Releases Each Purge Individual Gaimmi Emitters 10 #'
I'
' It-3 10 6 C.
Radwaste Service Area Fan EF-A-9 Monthly Individual Camma Emitters 10-4
( }( }
11 - 3 10-6 D.
Auxiliary Building Stack Monthly Individual Camma Emitters 10-4 (2)(3)
Reactor llullding Stack (Cas Samples)
~
11 - 3 10-6 h
Weekly (Cluircoal Sample)
I-131 10-I2 (4)
I Monthly (Charcoal Sampic) 1,-133, f-135 10-III (cm)
Weekly (Particulates)
Individual Camma Emitters I
(at least fo r lla-1.a-140, I-131 10-II-(4) itnthly Composite S r--89 10'II
=
Q (Particulates)
Crosa a 10-
- (c=)
NM Quarterly Compositb S r-90 10~II o
mm (Pa rt i c ul a t es)
CM IJ
.