ML063190535

Tech Spec Pages for Issuance of License Amendment 172 Regarding Revision to Technical Specification 5.5.8 on the Inservice Testing Program

ML063190535
Person / Time
Site:	Wolf Creek
Issue date:	11/15/2006
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Donohew J N, NRR/DORL/LP4, 415-1307
Shared Package
ML062980230	List: ML062980233 ML063190535
References
TAC MC9726
Download: ML063190535 (2)

Text

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 5.5.8 Reactor Coolant Pump Flywheel Inspection Program (continued) radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year Intervals.

Inservice Testing Pro-ram 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 applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows: I ASME OM Code and applicable Addenda terminology for inservice testing activities Required Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months every 6 months*every 6 months Every 9 months Yearly or annually Biennially or every 2 years At least once per 7 days At least once per 31 days At least once per 921days At least once per 276 days At least once per 766 days At least once per 376 days At least once per 731 days b. The provisions of SR 3.0.2 are applicable to theabove required Frequencies and other normal and accelerated Frequencies specified as 2 years or less In the Inservice Testing Program for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and d., Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.I I-(continued)

Wolf Creek -Unit I 5.0-10 Amendment No. 42,153, 172 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

i. Limitations on the annual and quarterly doses to a member of the public from iodine-1 31., iodine-1 33, tritium, and all radionuclides In particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle .sources, conforming to 40 CFR 190.k. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 3.9(N), cyclic and transient occurrences to ensure that components are maintained within the design limits.5.5.6 Containment Tendon Surveillance Program This program provides controls for monitoring tendon performance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural Integrity.

The program shall Include baseline measurements prior to Initial plant operation as well as periodic testing thereafter.

The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance critetia, shall be In accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC.The provisions of SR 3.0.3 are applicaible to the Tendon Surveillance Program Inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspebdton of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the Inner bore of the flywheel to the circle one-half of the outer (continued)

Wolf Creek -Unit I 5.0-9 Amendment No. 423, 153