ML20064M931
| 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) | |
Text
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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
- 4. A monthly proportional composite the following conditions shall be liquid waste sample, including met:
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 Sr-90, and gross alpha radio-shall be met.
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 fission and activated gases.
waste discharge valve 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 monitor shall be calibrated at 4.2 Discharge of radioactive wastes 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 instrument channel test monthly and are met:
a sensor check daily, a.
The minimum dilution water
- 8. The status and performance of required to satisfy 3.8.A.1 automatic isolation valves and shall be met.
discharge tank selection valves and results of indipendent liquid b.
Two independent samples shall 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 LIMITING CONDITIONS FOR OPERATION e
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 the statien under The radioactive controlled cendi:fons as part of p1sened operations.
liquid ef fluente vill be controlled on a batch basis and each *:stch vill be The limits in Specif: cation 3.F. A sampled and ::alyced prior to dischstge.
are defined to 1.cep radioactive esterial concer.::a: ions (above background) canal as lov as practicable and belov the limits given in in the dischsrgt 10 CFR, Part 20.
the concentration of Specification 3.E.A.1 requires the licensee te limit radioactive natorials in liquid effluer.ts fro: the station to levels
- 20. Appendix 5. for unrestricted creas. This specified in 10 CFT. Part 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.
for the relesse of radic-Specification 3.E.A.2 establishes an upper lini:
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 the public is provided a dependable source of operation te assure that in power under unususi operating conditions which may temporarily result
- he relesses higher than the levels normally achievabic when the sta:icn and liquid radesste equipment are functioning at designed.. The licensee has releases of up to 10 curies during any calendar quarter vill shown ths:
in cencentrations of radicactive esterial in liquid eff)uents at renu)t 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 of Specifics:fon 3.S.A.6. in addition to the requirements of Section '6.6, that the licensea sh.t11 identify 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.
and describe the proposed program of action to reduce such release rate.
I nust he filed within 3C days following the calendar quarter in This report 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 l
basis of operating experience at other similar nuclear power' plants.
l Specification 3.8. A.4.1 & 3.8. A.4.2 requires that suitable equipment to 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
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