ML20244B568

From kanterella
Jump to navigation Jump to search
Responds to 800814 Request for Review of Standby Gas Treatment Sys Testing Requirements.Followup Insp Scheduled to Assure That Leak Testing of Installed Housing & Ductwork Has Been Performed
ML20244B568
Person / Time
Site: LaSalle, 05000000
Issue date: 08/18/1981
From: Baer R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Spessard R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML16342B348 List: ... further results
References
FOIA-87-121 NUDOCS 8108280501
Download: ML20244B568 (2)


Text

  • .

i

. .. i(L... -i

... e 9" "' C

%- g PRINCIP S_T/JF f 5 9,( d j . NUCLEAR REGULATORY COMMISSION

-5

.p ny WASHWGTON, D. C. 20555 7/D gg,

\ ***

[ //}qKC 0 4 ggO [ '

9Od 4,nt Ak M g 3 3 1981 " It M DESTI prP

~

W  ?!le

~~~~

Docket No. 50-373 b o- [d MEMORANDUM FOR: [L. Spessard, Director, Division of Resident and N ""

  • Project Inspection, RIII arrs .+ o g s .J u c.o. ~

FROM: R. L. Baer, Chief, Reactor Engineering Branch, DRRRI . _ _ . _

SUBJECT:

TESTING OF STANDBY GAS TREATMENT SYSTEMS AT LASALLE (AITS F03096680H07)

Your memorandum to E. Jordan dated August 14, 1980, requested a review of the testing requirements for the Standby Gas Treatment System (SGTS) at LaSalle. The concerns relate to leak testing of the SGTS during the preoperational phase, subsequent periodic inservice testingr and : leak' testing following maintenance activities.

A review of the Standard Review Plan Section 6.5.1, Paragraph II44.f and the referenced ANSI standards N509-1976 (Section 5.6) and N510-1975 (Section 6) indicates that leak testing of the filter housing and ductwork is required after installation. In discussion with D. Bangart and R. Bellamy, Effluent Treatment Systems Branch, NRR, it was agreed that LaSalle should perform an appropriate leak test of the filter housing and ductwork after installation.

H. Wong of nty staff has discussed this position with F. Reimann, Region III, and we note that Inspection Report 50-373/80-49 maintains this issue ~as an ,

"Open Item."

In regard to periodic or post-maintenance leak testing, we have discussed this with the Effluent Treatment Systems Branch and come to the conclusion that this leak testing is not required. The bases for this determination is: 1) the use of all-welded construction reduces the potential for leakage,

2) initial pre-operational pressure testing would identify installation /

construction deficiencies, 3) leakage could be observed or heard during the routine use or testing of the SGTS, 4) area radiation monitors are in place that would detect leakage under abnormal circumstances and the affected SGTS train would be isolated preventing additional leakage to the reactor building, and 5) neither ANSI standard N509-1976 nor N510-1975 specify periodic or post-maintenance leak testing.

Based on recent discusWns with F. Reimann, we understand that a followup i

hyuL _

CONTACT: H. J. Wong, IE 'U '

49-24767 p T <bFJ1 Il

, ht2.%osoD < [7j AUG 2 01981 a p {

pa-  ; )q

b.

R. L spessard inspection is planned in order to assure that leak, testing of the installed housing and ductwork has been performed. It you have additional questions, please contact this office. l We consider this Action Item F03096680 closed.

Whff R. L. Baer, Chief Reactor Engineering Branch DRRRI cc: E. Blackwood, IE E. Gallagher, IE F. Reimann, RIII W. Gammill, NRR R. Bangart, NRR R. Bellamy, NRR A. Bournia, NRR 1

y , .

k.

~

$. m %4

.c UNITED STATES l' NUCLEAR REGULATORY COMMISSION y, f ,i WASHINGT ON, D. C. 20555 g -

k ,,..* 'JAN 11 1983 MEMORANDUM FOR: J. Sniezek, Director, Division of Resident and Regional Inspection, IE FROM: R. Mattson, Director, Division of Systems Integration, NRR

SUBJECT:

.f CLARIFICATION OF APPENDIX J REQUIREMENT 5 - DEFINITION OF TYPE A TEST FAILURES PIFERENCE: Memorandum from J. H. Sniezek to R. J. Mattson, " Request for Clarification of Provisions to 10 CFR Part 50, Appen-dix J," dated December 29, 1981 Sections III.D.1.a. III.D.2.a and III,D.3.a of Appendix J require that a set of three periodic Type A tests be performed at approximately equal intervals during each 10-year service period, and that Type B and Type C tests be per- -

formed during reactor shutdown for refueling but in no case at intervals greater than two years. Under these test requirements, there are many occa-sions when Type A, B and C tests must be performed during the same reactor shutdown period. Questions are frequently raised concerning the correct se-quence of conducting the Type A. Type B and C tests, and the potential impact-on the success or failure of a periodic Type A' test. With regard to these questions, the following clarification is provided by the Containment Systems Branch.

Type B and C tests could be performed either prior to the start of or after completion of the periodic Type A test provided that the pre-test requirements of III. A.l.a of Appendix J are met; i.e., no repairs or adjustments.-(ras) to the primary containment boundary are made so that the containment can be tested In as close to the "as is" condition as-practical. As such, the leakage infor- ,

nation obtained from the "as is"'(sometimes called "as found") Type A test can be used to assess the c.ontainment condition and its integrity following a period of plant operation.

If ras, made as a result of the Type B and C testing programs, or other reasons, are made to the primary containment boundary prior to the Type A test sequence, local leak tests must be performed on the affected portion of the containment boundary to determine the leakage rates before and after the P,As. The'"as '

fonnd" Type A test result can then be obtained by adding the differences be-tween the affected path leakages before and after ras, to the overall measured Type A test result. A periodic Type A test should be called a " failure" if the "as found" Type A test result (with or without correction from local leak tests) exceeds 0.75 La (maximum allowable leakage rate).

4WII f6057

Contact:

Y. Huang, CSO:DSI 29424