ML20213E490
| ML20213E490 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/29/1983 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0615, CON-WNP-615 NUDOCS 8308080682 | |
| Download: ML20213E490 (2) | |
Text
l h
^
/
j v_
MEMCRAflDUM FOR:
C. Thomas, Chief Standardization M d Special Projects Branch, LL FROM:
W. P. Butler, Chief Containment Systems Branch, DSI
SUBJECT:
RECOMMEftDED CHANGES TO THE !aP-2 TECHNICAL SPECIFICATIONS In your memorandum of July 1, 1933, you requested that we review thcse parts of the WNP-2 Technical Specificatipns that fall within our review responsibility. The following summarizes t.he changes we reccmmend:
1.
Items 4.6.1.2.C.1 and 4,6.1.2.C.3 of tn'e TS be changed per the attached memorandum.
2.
Item 3.11.2.8 to be changed as follows:
Venting or purging of the Mark II containment drywell shall bo through:
a.
A containment vent filtration system; or b.
The standby gas treatment system (SGTS).
Prior to the use of the purge system through the SGTS, t.ss$re that:
Both SGTS trains are determined to be operable whenever the a.
purge system is in use; and b.
Whenever the purge system is in use during oparating modes 1, 2, 3, only one of the two SGT3 trains may be ysed.
3.
Item 4.6.2.1, last paragraph (page 3/4 6-16) to be changed so as to require the test to be performed once per 9-months instead of 18-months.
4 Table 3.6.3-1 of the Technical Specificaticns does not incPade all the valves and all the testing requirements that were considerad during the FSAR review. We need the applicant to itemile all 6f the valves and their respective testing requirements as listed in Table s
6.2-16 of the FSAR; if some valves are appropriately excluded frcm Table 3.6.3-1, these should be identified and a rationale giwn for their exclusion.
N 7 p.
W. R. Butler, Chief 309080682 800729 Containment Evstemt 9 e ~w' ' ' h ADOCK 05000_397 s Division of fystems Integration
- s x
o,nc,
~"
sun w c)
.... A,t,t,ac,ha n t :., A.. s. s................. I d
om>
.....cci....See..p a ge. 2.......
pac rom m oo-w r.Gootact :
F. Eltawila CGihDIA129R33 CORD COPY m w-nwe
C. Thomas cc:
R. Mattson R. Houston A. Schwencer R. Auluck D. Hoffman distribution central file csb rdg file wbutler jkudrick feltawila
/
)
s
.CSE:.D." f...CS3;.2SI.....~.. CSS 0Slu ornce>
l...nr, \\..,%1 r. Lcg...
..ugut4en.......
su:r<=:n >.FC.1 i
..ufaa.......u....,caa..
.....u.:. 2sa.....
om>
'.RG FORM 315 (10-A) t. ACM c 4a OFFlClAL RECORD COPY uam 4.ii-naa
[pq
~~
'o UNITED STATES
,8p^,(;,g NUCLEAR REGULATORY COMMISSION O
t WASHINGTON, D. C. 20555
'bh
+...+
MAR 1 ISS3 MDt0RANDUM FOR:
C. Thomas, Chief Standardization and Special Projects Branch, DST FROM:
W. Butler, Chief Containment Systems Branch, DSI SUBJECT :
RECOPt4 ENDED CHANGE TO THE STANDARD TECHNICAL SPECIFICATIONS Surveillance requirement 4.6.1.2. Item C.1 of the Standard Technical Specifications, which is identical to Item III.A.3.b of Appendix J to 10 CFR Part 50 is not well worded since if the test is properly perfomed, the difference between the supplemental and the Type A tests can never be 4 0.25 La.
Therefore, it is recommended that Item 4.6.1.2.c.1 of the Standard Technical Specifications be changed to rend either of the following two ways:
1.
"Confims the accuracy of the test by verifying that the containment leakage rate, L'v, calculated in accordance with ANSI N 45.4 -1982 Appendix C, is within 25 per:ent of the containment leakage rate, Lv, measured prior to tae introduction of the superimposed leak"; or.
2.
"Confims the accuracy of the test by verifying that the supplemental test result, Lc, minus the sum of the Type A and the superimposed leak, Lo, are equal to or lesc than 0.25 La".
In addition, it is recommended that Item C.3 of the same surveillance re-(
quir.ements be changed to read as follows:
" Requires the quantity of gas injected into the contaiment or bled from the contaiment during the supplemental test to be between 0.75 La,snd 1.25 La".
The reason for this change is that Appendix C to ANSI N 451.4 - 1972 requires l
i the superimposed leakage rate to be approximately equivalent to La. The new ANSI /ANS 56.8 sets the limits between 0.75 and 1.25 La.
By copy of tnis memorandum, we recommend that these f:hanges be made a part I
of the Standard Technical Specifications fer both BWR's and PWR's.
L Walter R. Butler, Chief Contsiment Systems Branch Division of Systems Integration
+
h cc:
R. Mattson R. Houston M.
r R. B:ttimore CSB Hembers j
"^S
Contact:
F. Eltawilm, CSB:DSI, 23418
~
.