ML20097D099
| ML20097D099 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/10/1984 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| LIC-84-283, NUDOCS 8409170376 | |
| Download: ML20097D099 (19) | |
Text
Page 1 7
1984 REFUELING OUTAGE TYPE B AND C LOCAL LEAK RATE TEST
SUMMARY
As part of the 1984 refueling outage, local leak rate tests were performed on the reactor containment building penetrations in accordance with the Fort Calhoun Station Tc.hnical Specifications, (Section 3.5) and 10CFR50 Appendix J.
The testing is performed to identify, measure and if required, f.nitiate maintenance on potential reactor containment leakage paths; and to ensure the total measured leakage does not exceed the Technical Speci-fications limit of 0.6La, (La =_ Leakage allowable and.6La = 62,951 standard cubic centimeters per minute.) The initial "as found" local leakage which contributes toward the.6La limit and as measured from all local leakage paths was 29,520.79 secm.
(The individual leak rates for each penetration are tabulated on the attached TABLES I thru IV.) The final "after maintenance" leak rate was 7,684.33 scem.
The Type B tests were conducted by pressurizing the local containment penetration boundaries with air or nitrogen (air for the mechanical penetrations - nitrogen for the electrical penetrations) to Pa,. 60 psig accident pressure, and measuring the flow rate which is required to
. maintain the test volume at Pa.
This flow rate is assumed to be the ilocal containment leak-rate. The leak rate measurement system uses a
-we
-series of calibrated rotameters to determine the leakage.
The Type B tests are conducted to measure the leakage through the containment
- mechanical and electrical penetration seals, and containment building resilient sealed pr.netrations. _These tests are conducted as part of the Fort Calhoun Station Surveillance test program. All tests by which the
-following, leak rate data was obtained, are filed at the Fort Calhoun Station as Q.A. documents.
=The Fuel Transfer Tube leak rate test (ST-CONT-2, F.4) was conducted on 3/21/84, 4/28/84 and on 4/29/84. ~ The measured results are tcbulated on TABLE I (attached.) !!casured leakage of the Fuel Transfer Tube does contribute to the.6La leakage limit.
The Electrical Penetrations were leak tested in'accordance with ST-CONT-2,.F.5.
Results'are tabulated on TABLE IV (attached.) These penetrations do contribute to the.6La maximum allowable leakage limits.
The Mechanical Penetration sleeving was leak tested in accordance with
'ST-CONT-2, F.6.
Results are tabulated on TABLE V (attached.) This sleeving does contribute to the.6La maximum allowable leakage limit.
The Equipment-Hatch leak rate was tested as outlined in surveillance test 5:
ST-CONT-2, F.3.
Test were performed prior to its initial removal and following each replacement;'results are tabulated in TABLE II (attached.)
This leakage does contribute towards the.6La maximum allowable leakage limit.
8409170376 840910 1 h\\N PDR ADOCK 05000295 KW s
'lg P
Page 2 The Personnel Air Lock leak rate was tested in accordance with ST-CONT-2, F.1 (the reduced pressure test); these daily tests are on file at the Fort Calhoun Statione The personnel air lock (P.A.L.) was also tested two times since the previous refueling outage (once each six months per ST-CONT-2, F.2.)
Leakage is tabulated in TABLE III and does contribute towards the.6La leakage limit.
Type C tests were performed to measure the leakage of containment isolation valves.
(Refer to surveillance tests ST-CONT-3, F.1, F.2, and F.3.)
These tests are conducted using air as the test medium; with the exception of Penetrations M-9, M-12, M-16, M-91, M-93, M-94, M-96, and M-97, which use water as the test medium. Results of leak rates performed are tabulated on TABLE VI (attached.) Leak rates which do not contribute towards the.6La leakage limit are also outlined in TABLE VI.
The Mechanical Sleeves, valves or other containment penetrations which required cignificant maintenance are as follows:
Sleeve M-383-4, and valve penetrations M-10, M-14, M-22, M-24, M-30 M-51, M-69, M-87, M-88, M-93, M-94, M-95, and M-96.
The maintenance performed on each of the penetrations is listed below:
M-383-4 (Safety Injection Recirculacion " Submarine Hull" Mechanical Siceve.)
Measured leakage at the sleeve was found to be 1380 scem on 3/5/84. M.O.841106 was issued to lower leakage. A subsequent leak rate measured on 3/19/84 verified "0" scem leakage at this sleeve.
m M-10 (Steam Generator RC 2B Blowdown.) Initial leak rate measured through this penetration (3/9/84) was found to be 3000 secm. M.O.841100 and 841101 were written to rebuild blowdown valves HOV-1387A and HCV-1387B. M-10 was retested (4/2/84) and "0" seem was found.
M-14 (RC Drain Tank Vent to WDS.)
Initial leak rate measured through this penetration (3/17/84) was found to be 10,052.5 secm. This exceeds the maximum allowable leakage specified in TABLE I of ST-CONT-3, F.1 for penetration M-14.
M.O.841168 was written and new diaphrams were installed on HCV-507A and HCV-507B.
M-14 was retested on-5/1/84 and found to have 6.67 scem leakage.
M-22 (SI to and from Leakage Coolers.) Initial leak rate measured through this penetration (3/27/84) was found to be 2300 scem. M.O.840803 was written and it was found that valve needed packaging adjustment. Leakage was to the equipment drain header through a packing bleed-off line. M-22 was retested and found to
.have "0" sccm leakage on 3/9/84.
M-24 (Pressurizer Quench Tank Sample Line.)
Initial leak rate measured through
-this penetration (3/7/34) was found to be "0" sccm. However, the diaphram had signs of acid build-up. so M.O.841752 was written to replace the diaphram. The penetration M-24 was ratested 5/7/84 and found to have "0" sccm leakage.
M-30 and M-69 (Hydrogen Furge.)
Initial leak rat e measured through penetrations M-30 and M-69 was "0" secm (3/10/84.) New valves were instclied as part of a modification and the subsequent test showed excessive leakage. After maintenance, the v.lves were retested on 5/10/84 and found to have "0" leakage.
(;.
Page 3 tM-51 (Containment Pressure Signal.)
Initial leak rate measured'through this penetration on.3/14/84 was found to-be 2250 scem. M.O.841169 was written to install new diaphram. Penetration M-51 was retested 4/26/84 and found to have 13.7 seem leakage.
M-87 ((Containment Purge Exhaust.)
Initial leak rate measured through this penetration on 2/24/84 was found to be 2200 secm. M.O.841109 was written to adju'st' seals on PCV-742C. Leakage was found to be 102 sccm on 5/9/84. Purge valves wete again used so another leak rate had to be performed. Leakage was 2700 seem on 6/29/84.
M (Containment Purge Inlet.) The initial leak rate on penetration M-88 was
~2250 sccm (2/24/84.) After the valves were reclosed, the leak test on M-88 (5/9/84) showed 750 secm. The valves had to be used again for continued outage due to.the steam generator's repair. Excessive leakage was found so M.O.842223 was written to change the seal on PCV-742C. The leak rate on M-88 showed "0" leakage'on 7/1'/84.
M-93 and M (Feedwater.) On 3/14/84 and 3/10/84, the. initial leak rate test
.on penetrations M-93 and M-96, respectively, was 2250 sccm and.94 scfm. M.O.841846 J
fwas. written to adjust the limitorque on valves HCV-1103, HCV-1104, HCV-1385,
~
and HCV-1386. On 5/9/84 leak rate was 145 seem for M-93 and 850 scem for
. penetration M-96..
These valves do not contribute to the.6La maximum allowable 4,
4 leakage limit.
M-94 and M-95 (MSIV's.) On 3/9/84 and 3/11/84, the intital leak rates were 1800 sccm for M-94 and unmeasurable for M-95.
M.O.841097 and M.O.840353 were written to repair valves.
M-95's MSIV was not closing completely. After maintenance, the penetrations M-94 and M-95 were retested on 5/8/84 and found with "0" scem leakage.
The Fort Calhoun Station Unit No. 1 reactor containment building was subjected to e' third integrated leak rate test (Type A) during the period from January 6, 1983
.to January 10, 1983. The purpose of this test was to demonstrate the acceptability cof.the' containment building leakage rate at a' design basis accident internal pressure of 60.0 psig.. Testing was performed in conformance with the requirements of 10 CFR Part 50, Appendix J, and Fort Calhoun Station-Unit No. 1 Technical Specifications.
In-addition, the recommendations of ANSI 56.8 - 1981 and ANSI N45.4 - 1972, were g
~
considered.where appropriate.
? eakage rate testing was acceoplished at :he pressure level of 60.0 psig for a period Lof'10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. period was followed by a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> supplemental test for a verification of test instrumentation. The Type A integrated test results equal 52,826.29 sec/ min.
%4 L
.1
f._,
Pagn 4 2
e TABLE [I TYPE B TEST
. Fuel Transfer Tube-Leak Rate ~ Test '
(ST-CONT-2, F.4)
.s
' ~As.found~1eakage' measured-3-21-84 =
2 sccm
~
- As found leakage measured >:4-28-84 = 30C0 seem
,As found leakage measured 29-84 =-
1 seem e
A
- j. [J.
.'Y 'l j1*&T e
4
. NW
.*j.-
'[
-4 f
C O
i It
+
s j?
i.
c
.It g.
5
- 3. - i e oy t s,; ;
.,gg
v --
Paga 5.
a TABLE II TYPE B'TIST Equipment Hatch "0" Seal Test - (ST-CONT-2, F.3)
As Found As Left 3-- 5 ~ 0 scem 0 seem 3-29 2 secm-2 seem 4 84~:- O scem 0 seem f
. 5 7-84 -.O seem O seem k ' h *hNYj
~
s th ) $','r/':
5 k
1 u
4 4
A N
4.
b c
4 N
a NV'F'*4***"W*Y
1 v-Page 6
?.
e i
l 4
L. ' "
TABLE-'lII
. TYPE B TEST Personnel' Air: Lock Leak Rate Test (ST-CONT-2, F.2)
-Date' Tested-Leakage' Measured
- i
~
1-25-847
.3800 seem 1
.o 7-14 1950 secm -
s n- '
t 1
.i e
"f-_
s' $ 9 l
9F' ar r*
~
, n.:n > :M i h
+
r
+
4:-
e d
s
,C F
T l
k t
.A g
h
(*.
4 4
y P'
Y g.
T-g^
s
'(-
M, 'e Y-'-
E i i ' -
~
.......-._=.m.
cp ",
^
^ Foge -7 f.
rN*
\\
/
TABLE IV.
o
- TYPE B TEST
. Electrical Penetrations - (ST-CONT-2, F.5)
- Penetraiion -
As Fhund (secm)
As Left (scem)
~
A JO O
A-2 0-0 2
- A 4' -
0 0
i A-5 -;
O O
.A-61 0
0
-AN ' ~
0 0
si;4y%...: 74.sA-8 :
0-0
- A 0' 0
.wm i
- L. L A-10 ;.
- 0 0-0 4
- ' 11 0"
O' B-1:
0
.0 B-2I.
0
'O z
',h 0-0
- -:B '
LB-5 '.
O
~0
. 7
'~
J.-
f
.-B :0 0
i e
JB-7;
-0 0
B-8 0.
0
'.B-9 0-0-
i B - 10..
0 0
- y w
~ ** B-11.-
0' 0
d.
W.
4 1
4
+r 9
m
- ~.
~
~
'Paga 8
~
t:
L TABLE'IV (Con'inued) t
?:';
4 TYPE B TEST Electrical. Penetrations - (ST-CONT 2, F.5)-
~ Penetration-As Found (sccm)
As Left (sccm)
-lC-1 0
0 C-2
-0 0
C-4:
0 0
.**-C-5 0
0
.C-6 0'
0 il
' C-- 7.
0 0
7-
- C-8 0
0 y'f
'fr<<.
R t
'C-9 0
0
- -C-10 0
0 C-11 0:
0
- D 0.
0 D-2_
0 0
D-4~
0 0
- D-5 ~
0
- D-6 0'
O.
~D-7 0.
0 D-8' O
O
'D-9 0
0
.D.
'0 0
- D-11' 0
29.67 5.
b
~'
s heatu
- ps
,7 f,.; t
,Page' 9' u
. TABLE'IV-(Continued)
..2.
t TYPE B. TEST:
1 Electircal Penetrations - ' (ST-CONT-2, F.5)
Penetration-As'Found (sccm)
As Left (sccm)-
'E-1 0
0 1;
-' E-2 i
'0
- 0
~
=E-4 0
0 E-5
.0 0-E-6:-
0 0
E-7~
0 0
-E-8 0
0 E 0 0
I
-E-10 0
0
- n c;+ yu m -
- -: m
~
0
. **- E-11.-.
0 0-0 F-1:
i;pT i?AMMMJU#
>g.s, F-2 0
0
.p;.
o c;
, if '
~F-4' O;..
O.
4
,.e L' F-5..
0 0
p F-~6 0'
-0 y
4 I
-7.
~0 0
F 4
~)
F-8 -:
50
'0
- - F-9 '
O O
- F--l'0' 0
0 g.,
M-
~'
F - l' 2. 9.
12.9
.. G.0 0
LG 0 0
~ '
~
. G--3 i 0
0
~
"y fG 4-~
0 0
'r M
4 k#
[v fb"-
A
y, L.-
Page 10 B
5.
- D,
.:.l,
-D
- {
TABLE IV (Continued).
~
~
c..
~.
TYPE-B TEST-Electrical Penetrations '
(ST-CONT--2, F.5)
--As Found2(secm) is Left (secm)-
- H-1 0.
O H 0-0
~ :
.v h
- H-3E.
0 0
- H-41 0..
0 E-HCV-383-3A.-
4.33 4.33 E-HCV-383-3B-0-
0 E--HCV-383-4A 0-0
^
. m. h.
.iE-HCV-3'83-4B'"
~
0 0
4
% ' l;-
'~
JTOTALS =.
-17.23 46.9 i
F e
'*' These penetrations were : tested per ST-CONT-2, F.5 and also tested after
~
Linsta11ation of,the. penetrations installed-as part of modification 7 MR-FC-81-99 Part III.
Lik
.i '
4 I** These[Jpenetrations were: tested per ST-CONT-2, F.5 and also-as per
~
.w O ',
. part of modification.MR-FC-80-19, af ter Eddy Current -testing-of Steam
~
Generators - A & B.
However, in. both cases leakage was 0 secm.
u I
5 T
.t
~.$
s 5
dy a
"f"-
V Y
7
?
d
"f*
.Page 11 i
c..
TABLE V a
TYPE ~B TEST
~
Mechan'ical: Sleeve Leak' Rate (ST-CONT-2, F.6)
- -Pene tration -
As 'Found (sccm)
As Left (secm)
- M.
0 0
0 0
-M-2
'M-3 0
0 M-4 ?
0 0
4M-5 0
0 1
M 0 0
~M-7 0
.O f.
cz.
M-8
-0 0
$M-9;
-0 0-^'
9+6 -
3 UI-10~
-0~
0' t +. v '
- .M.O'
- O' -
.M-12' ~
O' 0
~
- g_13 0'
0 lM-14 0-0
, ' 't fM-15, O '.
O e
~
c.;
- M-16 '.
0 0
~
- ).M-17 0-
.- 0
'. M-18 '
0 0-l-,
- M-19
.0 0
,M 0 0
LM-21 0
0 I M-22~-
IO-
'O 4
dsPIMif 1?ddV' -['wA4 'c
'LJ
v.
- e - +;.x
- .
';.5 y 3y 1
3.
4 J;. jf Page 12 1
. ~:
TEBLE V (Continued)-
- ~ '
TYPE B TEST
~
E Mechanicaf Sleeve Leak Rate '(ST-CONT-2,- F.6)
Pene't ra$1on'
- As Found (secm)
As Left (sccm)
M 0
.O M-24'-
'O 0-
-M-25 0
0 e
' 'M-26 0
0
- M-27 0
.O
-M-28 0'
O M-29_
0 0
~
M-30,
.0-0
--. #s.1..
M-31
^
0
.0
~ wpc
.M-32' O
O'
- M-33'-
0
~0 l-M-34~ -
0 0
f -35 0
0 M
0';
O
~
l-M ' M-3'7.
'O O
2 M 0 0
)M 0 0
- M M-40 0.
0
, + -
M -0 0
g 4
- M-42 0
0 M-43 0-0 M-44 0
0
- t I.
s
- % 2sns46 ~ 6 n A
"- - - s wn 1
g-Page 13 l-..'
TABLE V.(Continued)
TYPE B TEST
. Mechanical Sleeve Leal [ Rate (ST-CONT-2, F.6)
- Penetration -
As Found (sccm)
As Left (secm)
M-45 L 0
0 M-4'6-
,0 0
M :0 0
M-48, 6.66 6.66 y
'M-49 0
0 M-50 0
0
'M-51 0
0 M-52 43.2 43.2
~
M-53 0
0
- M-54 0'
0
.- m :;;;v,
M-55 0-0 W;
M 0 -M-57' O
0 M-58 0
0
.M-59 0
0
.M-66
.0 0
. M-61 --
0 0
!M 0 0
~M-63~
0 0
. M-64' 0
0 M-65 0
0 M-6'-
0 0
6 l
1" t-c
?.J h'O-h
- - - h - '..-
4
-Ir,-
r;.
'y,
,-c.-
~
Page'14
- n.
TABLE ~V (Continued)'
TYPE B. TEST s
Mechanical Sleeve'. Leak Rate '(ST-CONT-2 F.6)
~
l ~e
~~
. Penetration-
~.As Found (secm)
As Left (secm)
.M 0-0
-M-68' 0
0
'M-69 0
0
.M-70
0-0 1
M-71 O
O M-72-'
0 0
'M 0 O
l 3.-p. as e,-
~--=-
M 0 0
M-75' O cya. -
- ~
.M-76 0
0
'M-77 0-0 M-78;
~0 0
~
.M 0
-0 M 0 0
,_n.
M-81~'
0 0
r-M-82 0
0
.M-83 0
0
_g
~~
M-84:
0-0 V
1,.
f.
Jh-85 11.5 11.5 M-86.
0 0
'M-87 0
0
~M-88
-0 0
5:.w4a4, 2hl unl.s hr 6%s: wi e e
c
Page 15-TABLE V (Continued)'
TYPE B, TEST
^
Mechanical.-Sleeve Leak Rat (ST-CONT-2, F.6)
- 'As Found (secm)
As Left (secm)
-M-89.
0 0
,M-90._
0 0
M-91 0-0
'M-92 0
0
'M-93
- 0 0
--M-94i 0
0
.M-95 '
520 520
, va,e-r:
.M-96.
0 0
- M-97 0
0 j
j, j,
M 'O O
M-99l 0
0 M-383-3 0
0 t-
.M-383-4 1380 0
TOTALS =
1961.36 581.36 m
t'.b
.i_gg 4xdsds. ' _ s uli s o
p.
Page 16 TABLE VI TYPE C TEST.-
Piping-As left/'
~
' Penetration' As Found (secm)
After Maintenance (sccm)
M-2 0
0
.M-7 0
0
~M-8
-0 0
- . M-9 :-
0 0
1**:-M-10 3000 0
-M-11 0
0 M-12.
0 0
- ~ :M-13
.120 '
0-
~ M-14 10,052.5.
6'.67
~
' < -; a.'
l M-15.'
O O
M-16 70 70 0
0~
-M-18 i-:
- g_19_
0 0
M-20' 0
0 M-22
- 2300 0-M-24 0-1
~
M-25'.:
'0 0
s M-30 0
0
'~
M-31-1 0
0
- M-31 -0 0
[
M-38-1
.0 0
M138 2.6 2.6 M-39 0-0 M-40-1=
0-0 M-40 0 0
M-42$
0 0
2 c.5~ b d-C + ?,e
-~
i& '- sye
>v.,
..m--.
.---n-..--
,L.,--
- pw
- ...
Page'17f y
T E'..;;
-TABLE,VI-(Continued)'
TYPE C. TEST Piping As Left/
' Penetration.
As Found (secm)
Af ter Maintenance (sccm) c M-43' O
0 M-44:
".0 0
IM-45:
900 o
M-46-p 9.6 9,6-s0 M 46-2 0
-M-47-1_
0 0
4
' M-4'7 0.
O
~
250 M-48-1 250
~
4.5
~
M-48-21 4.5 0
-~
- M-49 5.6 0
- m26 M-50 0 O
M-50-2; O
2250 A e 4h
.M-51-1_
13.7 150
.M-51-2 48 0
M-52-1 0
T.
.M-52-2 200 0
3 :-
M-53:
0 0
s M-57-1 0
0
~M-57-2
.0 0
.[
M-58-1 0
0
'M-58-2 1100-0
-** M-63 90 0-
'M-59:
0 0
M-72:
N/A N/A M 0 0
M-74 0
0
,M 0 0
M 0 0
hrw_,l
.. + -
7
.:g V. -
Paga 18 TABLE VI (Continued)
-TYPE C TEST Piping-As'Left/
' Penetration As Found-(secm)
~ After Maintenance (secm)
-86'
-2000 2000 M-87 2200 2700 M-88 2250
.O M-89 0
0
- M-91 26 26
-.** M-93.
2150' 145
'** M-94 1800 0
1** M-95:
MAX 0
- M-96~
.94 scfm=
850 i**E -97 300-6.54 M
- HCV 383-3 0
0
.HCV 383-4' 0
'0 m
TOTALS =~
'23,739.2
'5,106.07'
- Penetration. leak rates referenced to this mark do not contribute towards'the.6La maximum allowable leakage.
NOTE: The totals listed above only. include those leakages contributing towards the.6La leakage limit.
C-le'ff,
. _h..
q'/.',-
s v
-e
On.3ha Public Power District 1623 Hamey Omaha, Nebraska 68102 402/536 4000 Septenber 10, 1984 LIC-84-283 Mr. James R. Miller, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Miller:
1984 Refueling Outage Type B and C Local Leak Rate Test Summary Pursuant to the requirements of Fort Calhoun Station Unit No.1 Technical Specification 5.9.3.e and 10 CFR 50, Appendix J, the Omaha Public Power District submits the attached report which summarizes the Type B and Type C Local Leak Rate Tests conducted during the 1984 refueling outage.
Sincerely, W
R. L. Andrews Division Manager Nuclear Production RLA/DJM/rh-W Attachment cc:
LeBoeu f, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. E. G. Tourigny, NRC Project Manager Mr. L. A. Yandell, Senior Resident Inspector 1
htA 45 5120 Employmen h qual Opportunity i