ML040140600

Amendment to Technical Specification 5.5 Programs & Manuals

ML040140600
Person / Time
Site:	Vogtle
Issue date:	01/12/2004
From:	Office of Nuclear Reactor Regulation
To:
References
TAC MB7933, TAC MB7934
Download: ML040140600 (4)

Text

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.17 Containment Leakage Rate Testing Program 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 shal be In accordance with the guidelines contained InRegulatory Guide 1.163, "Performance-Based Containment Leak-Testing Program," dated September 1995, as modified by the following exceptions:

1. Leakage rate testing for containment purge valves with resilient seals Is performed once per 18 months in accordance with LCO 3.6.3, SR 3.6.3.6 and SR 3.0.2.

2. Containment personnel air lock door seals will be tested prior to reestablishing containment Integrity when the air lock has been used for containment entry. When containment Integrity is required and the air lock has been used for containment entry, door seals will be tested at least once per 30 days during the period that containment entry(les) Is (are) being made.

3. The visual examination of containment concrete surfaces Intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed Inaccordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWL, except where relief has been authorized by the NRC. At the discretion of the licensee, the containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities such as tendon testing, or during a maintenance/refueling outage.

4. A one time exception to NEI 94-01, Rev. 0, "Industry Guidelines for Implementing Performance-Based Option of 10 CFR 50, Appendix Jo:

Section 9.2.3: The next Type A test, after the March 2002 test for Unit I and the March 1995 test for Unit 2, shall be performed within 15 years.

The peak calculated primary containment Internal pressure for the design basis loss of coolant accident, P., Is37 psig.

The maximum allowable containment leakage rate, L, at P., Is 0.2% of primary containment air weight per day.

(continued)

Vogtle Units 1 and 2

• 5.5-20 Amendment No. 130 Amendment No. 108

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Containment Leakage Rate Testing Proaram (continued)

Leakage rate acceptance criteria are:

a. Containment overall leakage rate acceptance criteria are

• 1.0 L.. During the first unit startup following testing Inaccordance with this program, the leakage rate acceptance criteria are < 0.60 L. for the combined Type B and Type C tests, and

• 0.75 L. for Type A tests;

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate Is

• 0.05 L. when tested at 2 P.,

2) For each door, the leakage rate Is 0.01 La when pressurized to 2P,.

The provisions of SR 3.0.2 do not apply to the test frequencies specified Inthe Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

5.5.18 Configuration Risk Management Proaram The Configuration Risk Management Program (CRMP) provides a proceduralized risk-Informed assessment to manage the risk associated with equipment Inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. The program shall Include the following elements:

a. Provisions for the control and Implementation of a Level 1 at power Internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

b. Provisions for performing an assessment prior to entering the LCO Condition for preplanned activities.

c. Provisions for performing an assessment after entering the LCO Condition for unplanned entry Into the LCO Condition.

(continued)

Vogtle Units 1 and 2 5.5-21 Amendment No. 130 Amendment No. 108

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Configuration Risk Management Program (continued)

d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Condition.

e. Provisions for considering other applicable risk significant contributors such as Level 2 Issues and external events, qualitatively or quantitatively.

Vogtle Units I and 2 5.5-22 Amendment No. 130 Amendment No. 108

Programs and Manuals 5.5 Sample Size Criteria

.4 PI 4% 2%

01 3 15 25 35 1 I Time After Initial Structural Integrity Testing of Containment, Years (Lift-Off Testing Schedule, Containment No. 1) 0 35 15 25 35 l 11Tim Afe Inta St u tu a In e rt Te t n of CotI n e t Year Time After In-Rial Structural Integrity Testing of Containment, Years (Lift-Off Testing Schedule, Containment No. 2)

Schedule to be used provided:

a. The containments are Identical In all aspects such as size, tendon system, design, materials of construction, and method of construction. The tendon system for Unit 2 does not provide for detensioning. Detensioning can be performed only on the Unit I tendon system.

b. The 1-year Inspection for Unit 2 will consist of a visual inspection only. No lift-off testing will be performed on Unit 2 until the 3-year Inspection.

c. There Is no unique situation that may subject either containment to a different potential for structural or tendon deterioration.

d. The Unit 1 and Unit 2 surveillances may be performed back-to-back to facilitate detensioning of Unit 1 tendons during the Unit 2 surveillance.

Figure 5.5.6-1 Schedule of Ift-Off Testing for Two Containments at a Site Vogtle Units 1and 2 5.5-23 Amendment No. 130 Amendment No. 108