ML18152B545

Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels

ML18152B545
Person / Time
Site:	Surry
Issue date:	02/16/1999
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18152B544	List: ML18152B543 ML18152B545
References
NUDOCS 9902220351
Download: ML18152B545 (7)

Text

ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATIONS CHANGE VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

-- -9902220351 990216 PDR ADOCK 05000280 p PDR

TABLE 4.2-1 SECTION A. MISCELLANEOUS INSPECTIONS Required Required Examination Examination JO-Year Item No. Area Methods Interval Inspection Remarks I. I Deleted 1.2 Low Head SIS Visual Non-applicable This pipe shall be visually piping located inspected once per 18 months.

in valve pit 1.3 Primary Pump See remarks See remarks ExaFHiRatioR to be eonc:ltteted Flywheel in accgrdance with regulatgry pgsitioR C.4 .b of reg1:1latory guide 1.14 Re*,. I, A1:1gt1st l 97S 1.4 Low Pressure Visual and See remarks I 00% of blades every six operating Turbine Rotor Magnetic years. Inspections are normally Particle or performed concurrent with LP turbine Dye Penetrant rotor disk and hub inspections.

7 z0 Inspect once every 1O years by a qualified in-place (I]

. UT examination over the volume from the inner bore *of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces defined by the volume of the disassembled flywheels.

ATTACHMENT 3 REVISED TECHNICAL SPECIFICATIONS VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

TABLE 4.2-1 SECTION A. MISCELLANEOUS INSPECTIONS Required Required Examination Examination 10-Year Item No. Area Methods Interval Inspection Remarks 1.1 Deleted 1.2 Low Head SIS Visual Non-applicable This pipe shall be visually piping located inspected once per 18 months.

in valve pit 1.3 Primary Pump See remarks See remarks Inspect once every 10 years by a Flywheel qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces defined by the volume of the disassembled flywheels.

1.4 Low Pressure Visual and See remarks 100% of blades every six operating Turbine Rotor Magnetic years. Inspections are normally Particle or performed concurrent with LP turbine Dye Penetrant rotor disk and hub inspections.

z 0

VJ

e ATTACHMENT 4 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

e SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Virginia Electric and Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed change to the Surry Units 1 and 2 Technical Specifications and determined that a significant hazards consideration is not involved. The proposed change reduces the inspection requirements for the reactor coolant pump flywheels as previously generically approved by the NRC and supported by WCAP-14535A, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination".

Reactor coolant pump motor flywheels have been subjected to an augmented inspection program that satisfies the requirements of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, "Reactor Coolant Pump Flywheel Integrity," dated August 1975. Regulatory Guide 1.14, prepared in response to a concern over overspeed of the RCP and its potential for failure, describes an acceptable method to ensure RCP flywheel integrity. These inspections include an in-place volumetric ultrasonic (UT) examination of the areas of higher stress concentration at the bore and keyway every 3 years, and a surface examination of all exposed surfaces and complete UT volumetric examination every 10 years.

A survey of Westinghouse Owners Group utilities including Surry reported on a total of 729 examination results. The survey found n*o indication which would affect the integrity of the flywheels. The inspection record, plus concerns over inspection costs and personnel radiation exposure prompted Westinghouse Energy Systems to prepare WCAP-14535A to demonstrate through fracture mechanics analysis that flywheel inspections can be eliminated without impairing plant safety. Therefore, Westinghouse Energy Systems prepared report WCAP-14535A to quantify the effects of eliminating flywheel inspections. The NRC has reviewed, evaluated and approved the technical basis of the report.

WCAP-14535A provides the technical basis for eliminating the augmented inspection of the reactor coolant pump flywheels and applies to all flywheels manufactured by Westinghouse. Although accepting the technical arguments presented in the report, the NRC only granted partial relief from the RCP flywheel inspection requirements, requiring a continued inspection on a ten year frequency.

Only the inspection of the RCP flywheel is affected by the proposed change. The affect of the proposed change on the structural integrity of the RCP flywheel is shown to be negligible in the technical basis of WCAP-14535A. In support of this conclusion, the following analysis is provided.

a) The reduction of the inspection requirements for the reactor coolant pump flywheels, as generically approved by the NRC and technically supported by WCAP-14535A, does not significantly fncrease the probability of an accident previously evaluated in the safety analysis report. The results of WCAP-14535A have been reviewed and evaluated with the technical basis accepted for referencing in license applications by Page 1 of 2

the NRC in their letter entitled "Acceptance for referencing of Topical Report

, WCAP-14535, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination," dated September 12, 1996.

The proposed Technical Specification change reduces the surveillance requirements (inspection) on the RCP flywheel. There is no change in the method of plant operation or system design. The WCAP-14535A report establishes that the proposed change has a negligible affect on the probability that the flywheel will fail given that the flywheels received preservice and inservice examinations as required previously. Therefore, the proposed change does not increase the probability of occurrence or consequences of any previously analyzed accident.

• b) The proposed change to reduce the inspection requirements for the RCP flywheels as generically approved by the NRC and supported by WCAP-14535A does not create the possibility of a new or different kind of accident from any accident previously evaluated in the safety analysis report.

The proposed surveillance requirements (inspection) only reduce the inspection requirements/frequency for the reactor coolant pump flywheels, and there is no change in the method of plant operation or system design.

c) The proposed change reducing the inspection of the RCP flywheels as generically approved by the NRC and supported by WCAP-14535A, does not impact the accident analysis assumptions or the basis of any Technical Specification. As previously stated, the analysis performed in the WCAP-14535A report established that the affect on flywheel failure probability was negligible given that the initial preservice and inservice inspections under the current requirements were performed. Therefore, the proposed change in surveillance (inspection) frequency does not involve a significant reduction in the margin of safety.

The analysis provided herein demonstrates that the proposed amendment to the Surry Technical Specifications does not involve a significant increase in the probability or consequences of a previously evaluated accident, does not create the possibility of a new or different kind of accident, and does not involve a significant reduction in a margin of safety.

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