ML17340A810

Tech Spec Table 4.2-1 Item 7.1 for Reactor Coolant Pump Flywheel.Safety Evaluation Encl

ML17340A810
Person / Time
Site:	Turkey Point
Issue date:	03/05/1981
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17340A809	List: ML17340A808 ML17340A810
References
NUDOCS 8103110513
Download: ML17340A810 (4)

Text

TABLE 4.2-1 (CONTINUED

~

Extent of Examination Extent of Examination Examination Components and Parts (Percent in 10 Year Percent in 5 Year Item mo. ~tete ot To be Examined Method Interval) Interval) . Remarks 6.5 C-2 Prcssure"retaining Visual and 100X 33X Exception is taken for valves which are bolt. Volumetrio not accessible.'.6 K-1 Integrally-welded Not Applicablc Not Applicable supports 6.7 K-2 Supports and Hangers Visual 100X 33X Exception is taken for supports and hangers which are not accessible.

7.1 Reactor coolant pump flywheel 100X(2) In-place at bore Inservice inspection shall be performed on and keyway (1) ..each reactor coolant pump flywheel during the refueling or maintenance shutdown poinciding with the In-Service Inspection schedule as required by Seotion XI of the AMSE Boiler and Pressure Vessel Code:

(1) An in-place ultrasonic volumetrip examination of thc area of higher stress Conpentration at the bore and keyway at approximately 3-year intervals.

(2) A surface examination of all exposed surfaces and complete ultrasonic examination at or near the end of each 10-year interval.

7.2 Irradiation Tensile and Sce Remarks See Remarks Capsule 1 shall be removed and examined at Speciment Schedule Charpy V the first region replacement. Capsule 2 Notch (Wedge shall be removed and examined at the fourth Open Loading) region rcplaccment. Capsule 3 shall be removed and examined after twenty years of operation. Capsule 4 shall be removed and examined after thirty years of operation.

Capsule 5 shall be removed and examined after forty-years of operation.

3/5/81

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SAFETY EVALUATION RE: Turkey Point Unit Nos. 3 8 4 Docket Nos. 50-250 and 50-251 Pro osed. Tech S ec Amendment Introduction This evaluation supports a proposal to revise Specification 4.2. 1,

".Reactor Coolant System In-Service Inspection", Table 4.2-1,. Item No. 7. 1 Reactor Coolant Pump Flywheel Inservice Inspection, to conform to the the requirements of Regulatory Guide No. 1. 1'4, Revision 1, August 1975, and Section XI of the ASME Boiler and .Pressure Vessel. Code..

I I. Di scussi on The proposed revision to Technical Specification 4.2.1, Table 4.2.1, Item Ho. 7.1's necessary to conform Speci'fication 4.2.1 to the requirements of Regulation Guide 'No. 1.14 and Section XI of the ASME Boiler and Pressure

'Vessel Code. This proposed revision does not alter. the design philosophy for In-Servi'ce Inspection discussed in FSAR Secti'on 4.4.1 and as such will continue,to.ensure that as a mimimum, the assumptions used in the safety analyses are met and the operabili.ty of the reactor coolant pump flywheels are maintained.

I I I I. Conc 1 usi on, Me have concluded, based on the considerations discussed, above, that:

'(1) the. amendment does .not involve a significant increase in the probability or consequences of accidents, previously considered and: does not involve a significant decrease in a safety, margin, (2), there is reasonable'ssurance that the health. and safety. of the publ.i.c will not be endangered by operation in the proposed manner, and (3) such activities will be conducted'n compliance with the Commission' .regulations and the issuance of this amendment, will. not be inimical to the common defense and security or to the

.health and: safety:of the pub.lic.

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