ML17300B191

Proposed Tech Specs Modifying Requirement to Continuously Monitor Concentrations of Hydrogen or Oxygen in Waste Gas Holdup Sys

ML17300B191
Person / Time
Site:	Palo Verde
Issue date:	02/02/1988
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17300B190	List: ML17300B189 ML17300B191
References
NUDOCS 8802100220
Download: ML17300B191 (3)

Text

CONTROLLED BY USER RAG IOACTIVE EFFLUEHTS EXPLOSIVE GAS MIXTURE LIMITIHG COHOITIOH FOR QPERATIOH 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume whenever the hydrogen concentration exceeds 4X by volume.

APPLICABILITY: At all times.

ACTION:

aO With the concentration of oxygen in the waste gas holdup system greater than 2 by volume but less than or equal to 4~ by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. With the concentration of oxygen in the waste gas holdup system greater than 4~ by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4 by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />..

c The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SVRVEIL'LANCE REOUIREMEHTS 4.11.2.5 y

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~'~]TRG'Ll.::"-'.D::" 0:".='2 RADIOACTIVE EFFLUENTS

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~.~ BASES GASEOUS RAOWASTE TREATMENT (Continued)

This specification applies to the release of radioactive materials sn gaseous effluents from each reactor unit at the site.

The minimum analysis frequency of 4/M (i.e. at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 4.11-2. This will eliminate taking double samples when quarterly and weekly samples are required at the same time.

3/4. 11. 2. 5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained'n the waste gas holdup system is maintained below'the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability lipits. These automatic control

/

hovers, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of.

radioactive. materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4. 11.2.6 GAS STORAGE TANKS

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This specification considers postulated radioactive releases due to a waste

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gas system leak. or failure, and limits the quantity of radioactivity contained

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in each pressurized gas storage tank in the GASEOUS RAOWASTE SYSTEM to assure

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that a release would be sub'stantially below the guidelines of 10 CFR Part 100 for a postulated event..

Restricting the quantity of radioactivity contained in each gas stor age tank provides assurance that in tile event of an uncontrolled-release of the

~ - tank's contents, 't~e resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. Thfs is consistent with Standard Review Plan ll;3, Branch Technical Position ETSB 11-5,-

"Postulated Radioactive Releases Oue to a Waste Gas System Leak or Failure,"

in NUREG-0800, July 1981.

3/4.11. 3 SOLID RADIOACTIVE WASTE This specification addresses the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS. CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, wast oil content, waste principal chemical constituents, and mixing and curing times.

3/4. 11. 4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and PALO VERDE - UNIT 1 S 3/4 il-5 gamma ~ sy ~ w