ML23227A127

Corrected Proposed Technical Specification 55.16 Changes (Markup)

ML23227A127
Person / Time
Site:	Callaway
Issue date:	08/15/2023
From:	Ameren Missouri, Union Electric Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML23227A125	List: ML23227A127 ML23227A128 ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak
References
LNRC-06830
Download: ML23227A127 (1)

Text

Attachment 1 to ULNRC-06830 Page 1 of3 Attachment I Corrected Proposed Technical Specification 55.16 Changes (Markup)

(2 pages follow this cover sheet)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued)

c. Provisions to ensure that an inoperable supported systems Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.16 Containment Leakage Rate Testing Program

a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regul3tory Guide I I 63, Performance Based Containment Leak-Test Program, dated September 1995, Nuclear Energy Institute (NEI) Topical Report (TR) NEI 94-01 Industry Guideline for Implementing Performance-Based Option of JO CFR 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01 Revision 2-A, dated October 2008, as modified by the following exceptions:

(continued)

CALLAWAY PLANT 5.0-19 Amendment No. 22

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued)

I . The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWL, except where relief has been authorized by the NRC.

2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWE, except where relief has been authorized by the NRC.

& Thc unit is cxccptcd from post-modificotion intcarotcd lcakaae trnc tcstingrcquiremcnts ossociotcd wiin icum gcncrotor rcpi3ccment during the Refuel 14 outage (fall of 2005).

I flC IIFI I t\ 1CI nrrformca after the October 26, 1000 Type A

+k tect shall be performed frr October 25, 2014.

b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Da, 5 48.1 psig.

c. The maximum allowable containment leakage rate, La, at a shall be 0.20% of the containment air weight per day.

d. Leakage rate acceptance criteria are:

I . Containment leakage rate acceptance criterion is I .0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and 0.75 La for Type A tests;

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is 0.05 La when tested at a;

b) For each door, leakage rate is 0.005 La when pressurized tol0psig.

(continued)

CALLAWAY PLANT 5.0-20 Amendment No. 215