ML20206H030

Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing

ML20206H030
Person / Time
Site:	North Anna
Issue date:	05/03/1999
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20206H026	List: ML20206H022 ML20206H030
References
NUDOCS 9905110015
Download: ML20206H030 (3)

Text

e Attachment 2 Proposed Technical Specifications Bases Changes Nodh Anna Power Sudon Units 1 and 2 Virginia Electric and Power Company 9905110015 990503 PDR ADOCK 05000338 P PDR

3. . .-

4 l 3/4.6 ' CONTAINMENT SYSTEMS

'~

BASES

- 3/4.6.1 CONTAINMENT

_3f4.6.1.1 CONTAINMENT INTEGRITY

l. CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the l' containment atmosphere will be restricte'd to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction viith the leakage rate limitation, will limit I

(

! the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

l Lerkage integrity tests in the containment purge lines and the containment vacuum L ejector system lines is to identify excessive degradation of the resilient seats of these valves. These I tests will be performed in addition to the Type C tests required by 10 CFR Part 50, Appendix J and will not relieve the responsibility to conform with Appendix J. j E

I 3/4.6.1.2 CONTAINMENT LEAKAGE .

The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, Pa. As an added conservatism, the measured overallintegratedleakage rate is furtherlimited to less l

than or equal to 0.75 Laduring performance of the periodic test to account for possible degradation I of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements

, of Appendix "J" of 10 CFR 50. The containment is tested by performing leakage rate testing as required by 10 CFR 10 Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163 dated September 1995 or other NRC approved leakage rate testing methodologies.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate foi the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 and '/4.6.1.5 INTERNAL PRESSURE AND TEMPERATURE The limitations on containment internal pressure and average air temperature ensure that l) The containment pressure is prevented from reaching the containment lower design pressure of 5.5 psia for an inadvertent containment spray actuation, NORTH ANNA - UNIT I B 3/4 6-1 Amendment No. M87H6,

1 l4 g, 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY CONTAINMENT INTEGRITY e' sures n that the release of radioactive materials from the ,

containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

Leakage integrity tests in the containment purge lines and the containment vacuum ejector system lines is to identify excessive degradation of the resilier.t seats of these valves. These tests will be performed in addition to the Type C tests required by 10 CFR Part 50, Appendix J and will not relieve the responsibility to conform with Appendix J.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensme that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L aduring performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of

. Appendix "J" of 10 CFR 50. The containment is tested by performing leakage rate testing as l required by 10 CFR 50 Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163 dated September 1995 or other NRC approved leakage rate testing methodologies.

3/4.6.1.3 CONTAINMENT AIR LOCKS .

The limitations on closure and leak rate' for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the airlock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 and 3/4.6.1.5 INTERNAL PRESSURE AND TEMPERATURE The limitations on containment internal pressure and average air temperature ensure that B 3/4 6-1 Amendment No. 94;-99, NORTH ANNA - UNIT 2

.