ML20128E847

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 1.1.5 Re ODCM,1.1.6 Re Process Control Program Implementation of Programmatic Controls for Radiological Effluent TS & 1.17 Re Gaseous Waste Treatment
ML20128E847
Person / Time
Site: Crane Constellation icon.png
Issue date: 01/29/1993
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20128E821 List:
References
NUDOCS 9302110105
Download: ML20128E847 (1)


Text

1.9 DELETED 1.10.

DELETED 1.11 DELETED 1.12 DOSE EQUIVALENT l-131 The DOSE EQUIVALENT l-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1 134 and 1-135 actually

) resent. The thyroid dose conversion factors used for this calculation shall ac those listed in Table til of TID 14844, " Calculation of Distance factors for Power and Test Reactor Sites".

[0r in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.)

1.13 SOURCE CHECK A SOURCE CHECK-shall be the qualitative assessment of _ channel response when the channel sensor is exposed to a radioactive source.

1.14 DELETED 1.15 0FFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology _and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent,-in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and-in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radiological Environmental Monitoring Program required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.3 and 6.9.4.

1.16 PROCESSCONTROLPROGRAM(PCP)

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and:

packaging ~of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastos will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71,' State regulations, burial ground requirements, ano other requirements governing the disposal _of_ solid radioactive waste.

1.17 CASE 0VS RADWASTE TREATMENT The CASE 0VS'RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous _ effluent by collecting primary coolant system off gases from the-primary system and providing for delay or holdup for the purpose of reducing-the total radioactivity prior to release to the-environment.

L l

1-6 Amendment No. 72, 137 1

-9302110105 930129 l

DR ADOCK'0500 9