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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SECONDARY CONTAINMENT-BYPASS'LEAYAGE PATHS l- .

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$ X-93 Accumulator Sample Auxiliary Area X-94ABC Radiation Sample - Auxiliary Area .

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X-400 Hydrogen Purge Auxiliary Area- a

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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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^ \ PROPOSED TECHNICA!. SPECIFICATION [

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

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,,. 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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