ML20064M931: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:..
{{#Wiki_filter:}}
LIMITING CONDITIONS FOR OPERATION
* SURVEILLANCE REQUIREMENTS 3.8.A      Liquid Effluents (Cont'd)          4.8.A      Liquid Effluents (Cont'd)
: 3. The annual average concentration        3.
of tritium prior to dilution in a natural body of water shall not exceed 1 x 10-5 uCi/cc.
4.1    During release of radioactive wastes from the radwaste facility the following conditions shall be
: 4. A monthly proportional composite met:
liquid waste sample, including an aliquot of each bat,ch released during the month, shall be
: a. The minimum dilution water              analyzed for tritium, Sr-89, required to satisfy 3.8.A.1 shall be met.
Sr-90, and gross alpha radio-activity.
: b. The gross activity monitor and recorder on the radwaste effluent line shall be operable.
: 5. At least one representative
: c. The effluent control monitor            liquid waste batch per month shall be set to alarm and              shall be analyzed for dissolved automatically close the waste discharge valve fission and activated gases.
prior to exceeding the limits specified in 3.8.A.1      6.
above.
: d. Liquid waste activity and flow rate shall be contin-                                                  +
ually monitored and recorded during release.                    7. The liquid effluent radiation 4.2 Discharge of radioactive wastes              monitor shall be calibrated at least quarterly by means of a check may be made from any point other            source and annually with a known than the radwaste facility during            radioactive source. Each monitor, normal operations on a batch                as described, shall also have an basis if the following conditions are met:
instrument channel test monthly and a sensor check daily,
: a. The minimum dilution water        8. The status and performance of required to satisfy 3.8.A.1 shall be met.                          automatic isolation valves and discharge tank selection valves and
: b. Two independent samples shall results of indipendent liquid waste samples shall be checked and be obtained and analyzed              logged.
prior to discharge.
: c. Calculations of effluent flow shall be performed and in-dependently verified.
: d. Independent verification of applicable valve line ups shall be made.
8209080161 820830 PDR ADOCK 05000293 P                  FW@                                                              178
 
e e
LIMITING CONDITIONS FOR OPERATION
    '                                              SURVEILLANCE REQUIREMENTS 3.8.A    Liquid Effluents (Cont'd)
: e. All inputs to the batch to be discharged shall be isolated and no other release of radioactive waste discharges shall be allowed at the same time.
: f. While the discharge is in progress it shall be contin-uously attended.
  ~
: 5. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process, as a minimum.
all liquids prior to their dis-charge when the activity released during any calendar quarter ex-ceeds 1.25 curies.
: 6. When the release rate of radio-active liquid effluents, excluding tritium and noble gases, exceed 2.5 curies during any calendar quarter, the licensee shall notify the Director, Directorate of Licensing within 30 days' identifying the causes and describing the p'roposed program of action to reduce such release rates.
i l 178a Amendment No.
 
                . .                  .                                              ..                    . ..    .l..        ,
b EASES:                                    ,
3.8.A and 4.8.A Licuid Effluents.
Liquid radieactive r.aterial is released periodically from                                    Thethe      statien under controlled cendi:fons as part of p1sened operations.                                              radioactive liquid ef fluente vill be controlled on a batch                  The basis        limits and  each cation in Specif:      *:stch 3.F.
vill beA sampled and ::alyced prior to dischstge.
are defined to 1.cep radioactive esterial concer.::a: ions (above background) in the dischsrgt canal as lov as practicable and belov the limits given in
!                      10 CFR, Part 20.
Specification 3.E.A.1 requires the licensee te limit the concentration of radioactive natorials in liquid effluer.ts fro: the station to levels specified in 10 CFT. Part 20. Appendix 5. for unrestricted creas. This specifiesticn provides ascurance that no p.ctbcr of the general public can he exposed te liquids containing radioactive esterials in execss of limits considered permissible under the Cc= ission's Rules cnd Reguis tions.
Specification 3.E.A.2 establishes an upper lini: for the relesse of radic-active liquid effluen:s. excluding tritium and nobic gases, of 10 curies                                          The during any calendc quarter vi:hout specific Cc= ission approval.
intent of this specificatien is to permit the licensee the firxibf)fty of
            -            operation te assure that the public is provided a dependable source of in power under unususi operating conditions which may temporarily result relesses higher than the levels normally achievabic when the sta:icn and :he liquid radesste equipment are functioning at designed. . The licensee has shown ths: releases of up to 10 curies during any calendar quarter vill renu)t in cencentrations of radicactive esterial in liquid eff)uents at small perecntages of the limits specified in 10 CFR Part 20; i.e.
approximately one percent on an identified isotope basis.
In nddition to the limiting conditiens for operatien listed cadcr Speci-fication 3.6.A.2, the reporting requirecents that                              of Specifics:fon the licensea3.S.A.6.          in sh.t11 identify addition to the requirements of Section '6.6, the enuse whenever the release rate of radioactive ef fluen:s, cr.eludinr.
t rf t f um and nobic gases, exceeds 2.5 curies during any calendar cuarter.
I and describe the proposed program of action to reduce such release rate.
This report nust he filed within 3C days following the calendar quarter in which the 2.5 curie release occurred.
Specification 3.8.A.3 restricts' the release of tritium in radioactive liquids to less tha'n one percent of the concentration permissible by 10 l                        CFR Part 20. This release rate is considered as low as practicable on the basis of operating experience at other similar nuclear power' plants.
l l
to Specification 3.8. A.4.1 & 3.8. A.4.2 requires that suitable equipment l      dilute and monitor the releases of radioactive materials in liquid effluents are operating during any period these releases are taking place.
Releases of radioactive wastes from any point other than the radwaste facility shall be isolated and no other release of radioactive wastes shall be allowed i                        at the same time.
Specification 3.8.A.5 requires that the licensee shall maintain and operate the equipment installed in the radwaste system to reduce the release of 189
                                                .      8
                    , , ~ . . -
                            .                      . . ~ _ _ . - ,    . , - . . . --    ..,___._,._.-_.,-m-              -.m-.,        ,              _}}

Revision as of 11:00, 31 March 2020

Proposed Tech Specs Changes Allowing Controlled Liquid Effluent Releases from Points Other than Radwaste Facility
ML20064M931
Person / Time
Site: Pilgrim
Issue date: 08/30/1982
From:
BOSTON EDISON CO.
To:
Shared Package
ML20064M918 List:
References
NUDOCS 8209080161
Download: ML20064M931 (3)
v • d • e


Text

Retrieved from "https://kanterella.com/w/index.php?title=ML20064M931&oldid=2726580"