ML20086R209

LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual

ML20086R209
Person / Time
Site:	Seabrook
Issue date:	07/24/1995
From:	Drawbridge B NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20086R200	List: ML20086R197 ML20086R209 ML20086R211
References
NUDOCS 9507310055
Download: ML20086R209 (4)

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' Atlantic SEABROOK STATION UNIT 1 Facility Operating License NPF-86 Docket No. 50-443 License Amendment Request No. 95-03 Revision to Technical Specification 3.4.6.2 Reactor Coolant System Operational Leakage - Pressure Isolation Valve Table 3.4-1, (TAC No. M92959)

This License Amendment Request is submitted by North Atlantic Energy Service Corporation pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request: j Section 1 - Introduction and Safety Evaluation for the Proposed Changes l

Section II -

Markup of Proposed Changes  !

Section ill - Retype of Proposed Changes  !

Section IV - Determination of Significant Hazards for Proposed ChangesSection V - Proposed Schedule for License Amendment Issuance and EffectivenessSection VI -

EnvironmentalImpact Assessment Sworn and Subscribed to before me thi 84 _ day of ,1995 ruce L D wb

" Notary Public Executive Director - Nucles roduction 9507310055 950724 PDR ADOCK 05000443 l P PDR l

1. , Introduction and Safety Evaluation for the Proposed Channes '

A. Introduction The purpose of LAR 95-03 is to relocate Table 3.4-1, " Reactor Coolant System Pressure Isolation Valves" from Technical Specification 3.4.6.2, " Reactor Coolant System Operational Leakage" to the Technical Requirements Manual. The Technical Requirements Manual is the Nonh Atlantic controlled document developed to hold requirements relocated from the Technical Specifications.

Technical Requirement revisions are reviewed pursuant to 10CFR50.59 and summaries of changes are included with the periodic 10CFR50.59 report.

Relocating the Table from the Technical Specifications will eliminate the burden of processing License Amendments when changes are made to Pressure Isolation Valve (PlV) configurations and will facilitate the more effective utilization of NRC and North Atlantic resources, i

The Limiting Condition for Operation (LCO) and Surveillance Requirement will be changed to delete the reference to Table 3.4-1. Deleting the PlV Table from the Technical Specifications and relocating it to another controlled document is consistent with NUREG 1431, Revision 1, Standard Technical Specifications, Westinghouse Plants.

The " Applicability", " Action", and " Bases" sections of Technical Specification 3.4.6.2 were reviewed and are not affected by the proposed change.

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'l B. Safety Evaluation for Proposed Changes The proposed changes to Technical Specification 3.4.6.2 is administrative in that it relocates the PlV list from the Technical Specifications to the Technical Requirements Manual and maintains the requirements for PIV testing and the acceptance criteria for the testing in the Limiting Condition for Operation (LCO) 3.4.6.2(f).

As defined in 10 CFR 50.2,10 CFR 50.55a(c) and General Design Criteria 55 of 10 CFR 50, Appendix A, reactor coolant system (RCS) pressure isolation valves (PlVs) are any two normally closed valves in series with the reactor coolant pressure boundary, which separate the high pressure RCS from an attached low pressure system. The RCS PlV limiting condition for operation (LCO) 3.4.6.2(f) allows RCS high pressure operation when leakage through these valves '

exists in amounts that do not compromise safety. LCO 3.4.6.2(f) reads:

Reactor Coolant System leakage shall be limited to:

0.5 gpm leakage per nominalinch of valve si:e up to a maximum of 5 gym at a Reactor Coolant System pressure of 2235

• 20 psigfrom any Reactor Coolant System Pressure Isolation Valve specyled in Table 3.4-1 (with a footnote i addressing test pressures).

The basis for this LCO is the 1975 NRC " Reactor Safety Study" that identified potential inter-system LOCAs as a significant contributor to the risk of core melt.

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, The proposed relocation of Technical Specification Table 3.4-1 (loes not alter the requirements for pressure isolation valve operability currently in the Technical Specifications. -All PlVs will  :.

continue to be tested to the same rigorous requirements as defined in the Technical Specification : 1 Surveillance Requirements. Equipmem test methods, frequencies and acceptance criteria'are not .

affected.  !

l The proposed change does not make changes to the plant or in the method that any safety related -i system is tested or performs its safety function. The administrative change to relocate Technical l

. Specification Table 3.4-1 to the Technical Requirements Manual does not alter the basic -  !

regulatory requirement for RCS pressure isolation and will not affect the isolation capability for l credible accident scenarios. Future revisions to the Technical Requirement Table will be subject ' ,

to evaluation pursuant to 10CFR50.59.

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II., Markup of PrODOSed Chaptes See ' attached markup of proposed changes to Technical Specifications. The attached markup reflects the currently issued revision ofTechnical Specifications. Pending Technical Specifications .;

or Technical Specilication changes issued subsequent to this submitte.1 are not reflected in the l enclosed markup. j i

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