ML20059F220

Proposed Tech Specs 4.6.1.2.a Change Requesting Exemption from Type a Tests Performed at 40 Plus or Minus 10 Month Interval

ML20059F220
Person / Time
Site:	Wolf Creek
Issue date:	10/27/1993
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20059F187	List: ML20059F184 ML20059F220
References
NA-93-0185, NA-93-185, NUDOCS 9311040180
Download: ML20059F220 (4)

Text

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,' Attachment IV to NA 93-0185 Page 1 of 4 I

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r ATTACHMENT IV -l PROPOSED TECHNICAL SPECIFICATION CHANGES 3

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. . Attachment IV to NA 93-0185 Page 2 of 4 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE SURVEILLANCE REQUIREMENTS 4 6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance wdh the criteria speci-fled in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month

• intervals during shutdown at a pressure not less than either Pa. 48 psig, or P t. 24 psig, during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection;

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I WOLF CREEK - UNIT 1 3/4 6-2a Amendment No. 33 I

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. .' Attachment IV to NA 93-0185 .

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3/4.6 CONTAINMENT SYSTEMS 1 t

BASES ,

i 3/4 6.1 PRIMARY CONTAINMENT  :

3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactrve materials from the containment atmosphere will be restncted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the i SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions. l 3/4.6.12 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total ,

containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, Pa . As an added conservatism, the ,

measured overall integrated leakage rate is further limited to less than or equalto 0.75 L aor 0.75 L . tas applicable, during performance of the periodic  ;

test to account for possible degradation of the containment leakage barriers between leakage tests.

For reduced pressure tests, the leakage characteristics yielded by measurements Ltm and L am shall establish the maximum allowable test leakage  ;

rate Lt of not more than La(Ltm/ Lam). In the event Qm/ lam is greater than 0.7, Lt shall be specified as equalto L a (Pt/Pa )  ;

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50.

• 3/4 61.3 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 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. 'I

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h WOLF CREEK - UNIT 1 B 3/4 6-1 ,

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.. .' -Attachment IV to NA 93'-0185 ,

Page 4 of 4 l INSERT A 'i t

A one time extension of the test interval is allowed for the third Type A test of the first 10-year service period, provided that unit shutdown. l occurs no later than March 31, 1996, and performance of the Type A test  ;

occurs prior to unit restart following the eighth refueling outage. j INSERT B f A one time extension of the test interval is allowed for the third Type -;

A test of the first 10-year service period, as required by Surveillance Requirement 4.6.1.2.a and by Section III.D.1.(a) of Appendix J of 10 CFR 50, provided unit shutdown occurs no later than March 31, 1996 and- j performance of the Type A test occurs prior to unit restart following the eighth refueling outage. >

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