ML20204F182

Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A

ML20204F182
Person / Time
Site:	Davis Besse
Issue date:	03/09/1999
From:	CENTERIOR ENERGY
To:
Shared Package
ML20204F156	List: ML20204F151 ML20204F169 ML20204F182
References
NUDOCS 9903250231
Download: ML20204F182 (3)

Text

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i R 97-0001 Page 8 REACTOR COOLANT SYSTEM 3.4.10 STRUCTURALINTEGRITY ASME CODE CLASS 1. 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION j 3.4.10.1 The structural integrity of ASME Code Class 1,2 and 3 components shall be j maintained in accordance with Specification 4.4.10.1. j

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APPLICABILITY: AllMODES.

ACTION:

a. With the structural integrity of any ASME Code Class I component (s) not conforming to l the above requirements, restore the structural integrity of the affected component (s) to I within its limit or isolate the affected component (s) prior to increasing the Re ctor Coolant System temperature more than 50 F above the minimum temperature required by i NDT considerations.

b. With the stmetural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.

c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the component (s) to within its limit or isolate the affected component (s) from service.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5:

a. The-reacter ecclant pump flywhech sha!! be inspected per the recommendations of Regulatory Position CA.b. cf Regulatory Guide ! li, Rev;;ica 1, August 497-5_ Inservice insnection of each reactor _coolantnumo fivwheel shall beperformed at least once every 10 Sears. The inservice insneg} ion shall be either_atutltrasonic examination of the volume from the inner bore of the fivwheel to the circle of one-half the outer rmlius. or a sudace_ examination of exoosed_ surfaces of the disassembled flywheem recommendations delineated in Renulatory Guide _LIARevision 1. Aycust 1975, P_ositions 3. 4 and 5 of Section C.4.ttshall.pnpJL

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~9903250231 990309 PDR ADOCK 05000346 P PDR DAVIS-BESSE, UNIT 1 3/4 4-30

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L^;"" INFORMATION ONLY REACTOR COOLANT SYSTEMS SURVEILLANCE REQUIRE'4ENTS (Continued) b.

Each internals vent valve shall be demonstrated OPERABLE at least once per 24 months during shutdown by:

1. Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degrr.;ation,

2. Verifying the valve is not stuck in an open position, and

3. Verifying through manual actuation that the valve is fully open when a force of 1 400 lbs. is applied vertically upward.

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1 DAVIS-BESSE, UNIT 1 3/4 4-31 Amendment No. 23,95,165  !

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LAR 97-0001 Page 10 REACTOR COOLANT SYSTEM INFORMATION ONLY BkSES 3/4.4.10 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2 and 3 components, except steam generator tubes, ensure that the. structural integrity of these components' will be maintained at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains sufficiently '

covered. Inspection and manual actuation of the internals vent valves 1) ensure OPERABILITY, 2) ensure that the valves are not stuck open during normal operation, and 3) demonstrate that the valves are fully open at the forces equivalent to the differential pressures assumed in the safety analysis.

3.4.4.11 HIGH POINT VENTS- i Deleted l

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l DAVIS-BESSE, UNIT I B 3/4 4-13 Amendment No.-45,201