ML20247G947

Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years

ML20247G947
Person / Time
Site:	Vogtle
Issue date:	05/08/1998
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20247G940	List: ML20247G937 ML20247G947
References
NUDOCS 9805210017
Download: ML20247G947 (8)

Text

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e ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM REVISED TECHNICAL SPECIFICATION PAGES

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h VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECliNICAL SPECIFICATION 5.5,7 REACTOR COOLANT PUMP FLYWIIEEL INSPECTION PROGRAM l

l INSTRUCTIONS FOR INCORPORATING REVISED PAGES I

l The proposed change to the VEGP Units I and 2 Technical Specification should be incorporated as follows:

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5.0-12 5.0-12 5.0-12a 5.0-12b l

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Programs and Manuals 5.5 L

5.5 Programs and Manuals _( continued)

L 5.5.6 Prestressed Concrete Containment Tendon Surveillance Prooram This program provides controls for monitoring any tendon

! degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall incluoe l baseline measurements prior.to initial operations. The Tendon Surveillance. Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2, 1976.

L The provisions of SR 3.0.2 ano SR 3.0.3 are applicable tc the L

Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pumo Fivwheel Inspection Prooram t

"i: pr:gr:: :h:ll p : vide fee-the in:p:: tion-of-each re::t:r i'

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tier.; ef Regaleter, l

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>  : el::t ;^r- flyd.::1 p;r the r;;:

Fe;itier c.4.b ef Regeleter, Oside-1.14 Resisier,1, ".;;;st 1075.

t-5.5.8 Inservic3,Testino Prooram This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

l a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

l l ASME Boiler and Pressure Vessel Code and applicable Required Frequencies for

! Addenda terminology for performing inservice L inservice testino activities testino activities Weekly At least once per 7 days

! Monthly At least once per 31 days Quarterly or every 3 months At least cnce per 92 days Semiannually or every -At least once per 184 days n 6 months L Every 9 months At least once per 276 days L' Yearly or annually At least once per 366 days Biennially or every 2 years At least~once per 731 days (continued) 1

^vogtle Units I and 2 5.0-12 Amendment No. (Unit 1)

Amendment No.-f4-(Unit 2) l

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l INSERT This program shall provide for the inspection of each reactor coolant pump flywheel at i least once per 10 years by conducting either:

a.' An in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or

b. - A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump FlywheelInspection Program.

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. Programs and Manuals 5.5 5.51 Programs and Manuals (continued) 5.5.6- Prestressed Concrete Containment Tendon Surveillance Proaram This program provides controls for monitoring any tendon

- degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural-integrity. The program shall include baseline measurements prior to initial operations. The Tendon

- Surveillance Program, inspection frequencies, and acceptance-criteria shall be in accordance with Regulatory Guide 1.35, Revision 2, 1976.-

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pumo Flywheel Insoec'tion Proaram l This program shall provide for the inspection of each reactor coolant pump flywheel at least once per 10 years by conducting _

eithcr:

a. An in-place ultrasonic examination over the volume from the inner bore of- the flywheel to the circle of one-half the outer radius;.or

b. A surface examination (magnetic particle and/or liquid penetrant) of' exposed surfaces of the disassembled flywheel.

.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program.

5.5.8 Inservice Testina Proaram This program provides controls for-inservice testing of ASME Code Class 1, 2, and 3 components._ The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as

!- .follows:

(continued)

Vogtle Units l'and 2 5.0-12 Amendment No. (Unit 1)

Amendment No. (Unit 2) i j

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l Prograns and Manuals l 5.5  ;

5.5. Programs and Manuals (continued) l ASME Boiler and Pressurn Vessel Code and applica' ale Required frequencies for Addenda terminology for ' performing inservice .

JAtgrvice testina activities testina activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every At least once per 184 days i 6 months  !

Every 9 months At least once per 276 days )

Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days l l

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Vogtle Units I and 2 5.0-12a Amendment No. (Unit 1)

Amendment No. (Unit 2)

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- Programs and Manuals 5.5 5.5 . Programs and Manuals (THIS PAGE INTENTIONALLY LEFT BLANK) l l

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-(continued) 1 l

Vogtle Units 1 and 2 5.0-12b Amendment No. (Unit 1) )

!. Amendment No. (Unit 2)  ;

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! ENCLOSURE 4 i .

VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM ENVIRONMENTAL IMPACT DETERMINATION 10 CFR 51.22 (b) specifies the criteria for categorical exclusions from the requirement for a specific environmental assessment per 10 CFR 51.21 This license amendment request meets the criteria specified in 10 CFR 51.22 (c)(9) as demonstrated below:

Basis for Exclusion (1) The amendment involves no significant hazardt consideration.

As demonstrated in Enclosure 2, the proposed amendment does not involve any significant hazards consideration.

(2) There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

The proposed amendment does not involve a change to the facility or operating procedures that would cause an increase in the amounts of effluents or create new types of effluents.

(3) There is no significant increase in individual or cumulative occupational radiation exposure.

The proposed amendment would result in a decrease in individual radiation exposure by reducing the scope and frequency of RCP flywheel inspections.

Conclusion Based on the above, it is concluded that there will be no impact on the environment resulting from this amendment and the change meets the criteria specified in 10 CFR 51.22 (b) for a categorical exclusion from the requirements of 10 CFR 51.21.

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