ML20106E838

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Proposed Tech Spec Table 3.6-1, Secondary Containment Bypass Leakage Paths, Adding post-accident Sampling Penetrations & Deleting Integrated Leak Rate Test Penetrations X-27C & X-98
ML20106E838
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 10/22/1984
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20106E784 List:
References
NUDOCS 8410300140
Download: ML20106E838 (7)


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ENCLOSURE 1 E

PROPOSED TECHNICAL SPECIFICATIONS SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2

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. 9 SECONDARY CONI AINilENI BYPASS LEAKAGE PAllis e o p g 4- x-(. , PENEIRATION, RELEASE LOCATION h

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X-25A Pressurizer Gas Sample Auxiliary Area X-2SD Pressurizer Iiquid Sample Auxiliary Area

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, X-398 .N 2 to Pressurizer Relief Tank Auxiliary Area, a X-41 Normal RB Sunip Auxiliary Area X-42 Primary Water Auxiliary Area X-45 RC Drain Tank Auxiliary Area X-46 RC Drain lank Auxiliary Area i X-47A Glycol Auxiliary Area X-478 Glycol Auxiliary' Area X-SOA CCW Auxiliary Area X-SOB CCW , Auxiliary Area X-51 fire Protection Auxiliary Area X-64 A/C Chilled Water (ERCW) Auxiliary Area X-65 A/C Chilled Water (ERCW) Auxiliary Area X-66 A/C Chilled Water (fRCW) Auxiliary Area X-67 A/C Chilled Water (LRCW) Auxiliary Area X-76 Service Air Auxiliary Area X-77 Demineralized Water Auxiliary Area X-78 fire Protectioh Auxiliary Area X-81 kC Drain Tank Auxiliary Area X-82 fuel Pool Auxiliary Area X-83 Iuei Pool AuxiIiary Area l

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l{iEN vo 5- S TABLE 3.6-1 (Continued)

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SECONDARY CONTAINMENT-BYPASS'LEAYAGE PATHS l- .

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X-101 PASF Auxiliary Area

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. *This Technical Specification change is effective upon completion of the modification.

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    • ENCLOSURE 2 JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATIONS TVA-SQN-TS-61 Description This' proposed technical specification change revises table 3.6-1 to add postaccident sampling facility penetrations and delete integrated leak rate test penetrations X-27C and X-98.

Justification The postaccident sampling facility penetrations involved in this change are already included in the surveillance program, but they should be added to table 3.6-1 concerning secondary containment bypass leakage to ensure compliance with 10 CFR 50 Appendix J. Penetrations X-27C and X-98 should be deleted from the table since they only penetrate primary containment.

Based on the a'ttached significant hazards determination: (1) the proposed change does rot constitute a significant hazards consideration as defined by 10 CFR 50.92; (2) there is masonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Environmental Statement. ,

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SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION I TVA.,SQN TS-61

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c P ' 1.- Is 'the probability ofian occurrence or the consequences of an accident previously evaluated in the safety analysis mport significantly

,,. 1. increased? No. T' The added penetrations will not affect any safety-related equipment and have been added to the surveillance requirements for secondary bypass leakage. The deleted penetrations do not penetrate the seccndary bypass leakage boundary.

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2. Is the possibility for an accident of a new or different type than evaluated previously in the safety analysis mport created? No.

i The penetrations vers waled using approvp procedures. No new accident possibility was creat$d) sy

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Ts the margin of safety. significantly reduced?

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_s No safety-related equipment is changed nor is any surveillance reduced and ..:,

therefore, there is no impact on the margin of safety as defined in the

, basis V, any Technical Specification.

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