ML20076L603
| ML20076L603 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/13/1983 |
| From: | Cappuccio G, Murphy W, Phillips D VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| FVY-83-97, NUDOCS 8309160157 | |
| Download: ML20076L603 (31) | |
Text
{{#Wiki_filter:. . 4 VERMONT YANKEE PRIMARY CONTAINMENT LEAKAGE RATE TESTING 1983 TEST COORDINATORS David L. Phillips Gary Cappuccio PREPARED BY David L. Phillips Gary Cappuccio I hO(d g I 8309160157 PDR ADOCK 83091305000271 PDR R
Introduction During the 1983 refueling and 10 year inservice inspection outage which occurred during the period from March 5,1983 to June 17, 1983, a type A containment integrated leakage rate test was performed. This test fulfilled the Appendix J requirement to perform a Type A test during the ten year ISI outage. The last leak rate test report was filed with the USNRC in April, 1981. This report describes all primary containment leakage- testing performed subsequent to the 1980 Type A test, and up to and including the type A test conducted in June 1983. In accordance with 10 CFR 50, Appendix J, a summary analysis of all periodic Type B and Type C tests performed since December 1980 are included in this report. All testing performed during the period covered by this report conformed to the rules n'nd regulations specified in 10 CFR 50, Appendix J. Summary The plant was shut down on March 5, 1983 for refueling and the ten-year inservice inspection. The Type B and C testing commenced shortly before the plant shut down. The Type'A test was conducted at the end of the outage. Pressurization for the Type A test commenced on June 8,1983 with two air. compressors of 1800 scfm total capacity and approximately 5 psi /hr charging rate. Containment pressure was raised to the calculated peak accident pressure of 44 psig over an 11-hour and 36-minute period. During this time period the pressurization rate was reduced at the 5, 15, and 30 psig levels to facilitate investigation for containment leakage. No significant leaks were found during the pressurization period. After stabilizing for four hours, it was determined that stable conditions had been met to start the test at 0203. Based upon this, 0203 was chosen as the time _for star *ing the test.
~
The 24-hour test was com-pleted June 10, 1983 at 0202. The absolute method of leakage determination was employed. The ideal gas laws are utilized to find the mass of air in the containment at ten minute intervals. The containment mass was plotted against time and the, absolute leakage rate was determined from the slope of the least squares fit line (See Figure II). The measured leakage rate at the upper one sided 95% confidence level was 0.2172 Wt%/ day. The final corrected leakage rate at the upper one sided 95% confidence level was 0.318 Wt%/da,y.
Description of the Test The containment was made ready for the integrated leakage rate test and pressurization commenced at 1304 hours on June 8, 1983. Pressurization was accomplished by using two mobile, oil-free air compressors, each with a capacity of 900 scfm. They were connected by the hose to the nitrogen purge supply line at a tee, through VNP-1071, as shown on the attached Figure I. As the containment pressure reached the hold points of 5, 15, and 30 psig, the air flow into the containment was reduced and survey personnel were dispatched. ~The survey personnel found no significant leaks and the pressurizing rate returned to normal. During the pump-up, drywell pressure transmitter PT-1-156-3 was isolated and RRU3 and RRU4 were manually tripped. The pressure transmitter was isolated due to high pressure and the RRU's due to high amperage readings. One of the two oil-free air compressors tripped during the pressurization causing the lengthy pressurization period. The test pressure was attained at 2350 hours. Pressures and temperatures in the containment were allowed to stabilize for four hours. At the end of the four hours, revies of the data indicated that the stabilization criteria had been met since 0203 and the decision was made to make this time the start of the test. Due to the inability to obtain the equipment necessary to provide the pressure signal to the process computer, the contained mass was calculated by manually inputing the data into a timeshare program PCLRTP. Table 1983-A (Primary Containment Leakage Rate Data Sheet) contains
- 1) the results of the timeshare program (PCLRTP) contained mass calculations,
- 2) the containment pressure as read from the quartz manometer, and 3) weighted average drywell temperature.
The peak pressure Type A test was completed at 0202, June 10, ~983. A supplemental test, (required by Appendix J, 10 CFR 50) to verify the accuracy of the instrumentation was conducted by metering a mass of air approximately equal to 1/2 the allowable leakage back into the containment. This pumpback of 2313 lbs. was completed at 0300 hours. Containment depressurization commenced at 0445 hours.
Analysis and Interpretation of Test Data This test employed the ideal gas laws to determine the absolute leakage rate from primary containment. The total containment mass calculation was performed approxist.3.tely every ten minutes during the 24-hour test on the timeshare computer. Input data for the calculation consisted of containment pressure, drywell and torus weighted average air temperature, drywell and torus des points, and torus water level. The data (consisting of a series of independent calculations of the total contained air mass taken at ten minute intervals) lends itself to a statistical analysis based upon a time dependant rate of change of the contained mass of air. A small pressure change over the test interval is the basis for the assumptien that the containment leakage is constant with respect to time. A linear least squares fit method is utilized to determine the best straight line to fit the data. The slope of the least squares fit line is the leakage rate. The equation of the least squares fit line is of the form:
- 1. Q = b + r.T Where: Q = mass of air b = Q intercept (Q value at t = 0) m = slope of line (leakage rate)
T = time N = number of data points l The values for b and m are determined from the following equations: I b= IQ - MET N
"" N(EQT) - (EQ){ET)
N(ET') - (IT)' The upper one sided 95% confidence level (UCL) of the leakage rate (slope of line) may be determined from the standard error of the slope and a " Students Table of t". The standard error is: Standard Error, S(m) = -
-M l N2 a T 8(*) " N-2
'1 NIQ - (EQ) -M NET' - (ET)' . .
The upper one sided 95% confidence level on the true leakage rate is: UCL (approx.) = Lam + 2400 *(t.95)*(S(m)/b) (1) Where: UCL = Upper confidence level
Lam = -(2400)*(m/b) t.95 = The t factor at the 95% cenfidence level for 142 data points Variance = (Standard deviation) = (*' " n (1) ANSI /ANS 56.8 - 1980 App. B Test Results . A linear least squares fit of the 142 data points calculated during this test (presented in Table 1983-A), result in the following equation: Q = 73038 - 6.3732T Where: 73038 represents the initial mass of contained air in pounds 6.3732 represents the slope or leakage rate in the Ibm / hour f i The upper one. sided 95% confidence level of the Icakage rate using this data is: UCL = - Lam + 2400 (t.95)(S(m)/b)
- -(2400)(m/b) + 2400 (t.95)(S(m)/b)
=
-(2400) (-6.3732/73038) + 2400 (1.65) (.1449/73038)
= .2172 WT%/ day Correction Factors
- 1. Correction for loss through isolation valves CRD-181 RCU-68 = + .0137 Wt%/ day RCU 15
- 2. Correction for increase in drywell sump levels
+ .0279 Wt%/ day
- 3. Correction for increase in reactor vessel water level
, + .0596 Wt%/ day The corrected leak rate at the upper one sided 95% confidence level is 0.3181 Wt%/ day. This measured value is less than the Technical L Specification limit of 0.75 La, (where La = 0.80 weight percent of con-tained mass per 24 hours), which is equivalent to 0.60 weight percent
- of contained mass per 24 hours.
.- . , - , , em - -~--.---.--- - - - - - , . - - _ , .
-y. r--.- -o-..--,.--r--- -e-.. . - , -y_ _ , , , - .,
Verification of Instrumentation Sensitivity
, Section III.A.3 (b) of Appendix J to 10 CFR 50 requires that the I accuracy of the Type A Test shall be verified by a supplemental test. )
j The Pumpback Method of verification was selected. In this method, a known quantity (mass) of air is metered into the containment and is compared with the change in the calculated weight of air. The required accuracy between the metered quantity and the calculated quantity is i specified in Appendix J to be .25 La. t The quantity metered back was selected to be approximately equivalent to1/2theallowabgeleakage'rateof0.60Wt%/ day. The actual quantity metered was 618 Ft , 58 psig feed pressure and 60*F, which is equivalent t to 231.9 pounds mass. The average of five calculated values of mass of air prior to the charge was 72866.1 lbs. The average of five calculated values of mass of air following the charge was 73140.3 lbs.. During the 60 minute l elapsed time between before and after average measurements at the measured leakage rate of 6.503 lbm/hr, 6.5 lbs was assumed to leak during the pump back test.
-The balance is as follows:
)
-Mass following air charge 73140.3
. Mass prior to charge- 72866.1 Difference 274.2 i
" Normal Leakage" 6.5 1
Total Difference 280.7 The comparison to the actual charge ~of 231.9 lbs is:
- 280.7 - 231.9 =
49.8.lbs. difference. The allowable Supplement Test error of .25 La - 146.02 lbs. l The 49.8 lbs in the 1983 Supplement Test was well within the accuracy 1 limits specified in Appendix J. l
-- _ ._ _ _ _ ._ .__ - . ~ . _ _ _ , , - , - - _ _ _ , _ . - _ _ _ .
l Instrument Selection Guide Calculation The following calculations verify the ability of the instrumentation system to measure the integrated leakage rate of the primary containment system. Instrumentation errors are combined using a root-sum-square formula. 2 eT 1/2 (2) 2400 + ISG = + - t 2 (p/ *ll\) + 2(epv)2
\p 2 (5--) 2 -
ISG = instrument selection guide t = minimum expected test duration (hours) p = containment atmosphere total absolute pressure pv = containment atmosphere part pressure of water vapor T = containment atmosphere weighted average absolute drybulb temperature e = error associated with measurement of change in a given parameter The ISG shall not exceed 0.25 La (where La is the maximum allowable primary containment integrated leak rate). (2) ANSI /ANS 56.8 - 1980 A. Test Parameters La = 0.8%/ day P = 58.7 psia T = 550*R drybulb Tdp = 60*F dewpoint t = 24 hours B. Instrument Parameters
- 1) Total absolute pressure No. of sensors: 1 Range 0-150" Hg absolute (0-73.68 psia)
Measurement system error: f0.002% of F.S. = + 0.003 in Hg Abs = +.001 psia eP = 10.001 psia
- 2) Water vapor pressure No. of sensors: 4 Sensor sensitivity error (E +0.5"F Measurement sensitivity err 8r)(cpv)
Computer resolution = 0.1*F Computer repeatability = (40 my scale) = + .08% Therefore at 60*F 60*F x .0008 = 0.048"F At a dewpoint temperature of 60*F, the equivalent water vapor pressure (as determined from the steam tables) is 0.0092 psia /*F.
-- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
Epv = (10.5"F) (0.0092 psia /*F) = 10.0046 psia cpv = (10.048'F) (0.0092 psia /*F) = 10.00044 psia epv " 1 [(Epv) + (cpv) ] ! [(0.0046)2 + (0.00044) ]I! [No. of sensors] 1/2 [4] 1/2 epv = 0.0023 psia
- 3) Temperature No. of sensors: 19 Sensor sensitivity error (Et) = 0.5*F Measurement sensitivity error (ET) excluding sensor Computer resolution = 0.1*F Computer repeatability (40 my scale) = 10.08%
at 100*F 100*F x 0.0008 = 10.08'F E T
=
10.5'F = 10.5*R c = +0.08'F = +0.08'R
" [(E ) + (c.,,) ]! ~
[(0.5)2 + (0.08 )1/2 2
"T [No'of SensorA] 1/2 (19) 1/2 e =
1 0.1162*R T
- 4) ISG 2
1/2 ISG = 1 2( )2 + 2(* *) + 2 2 ~
=- 1 2400 2[0.'0013 + 2[0.0023)2 +2[0.11623 1/2 24 - M8. 7 / \ 58.7 / \ 550 / .
=
1100 [(5.8 x 10-10) + (3.07 x 10-9) + (8.9 x 10-8)) 1/2
=
1100 [9.29 x 10-8) 1/2 = 0.0305 ISG = 10.0305 Wt %/ day
.0305 Wt %/ day is less than 0.2 wt %/ day (.25 La); therefore, the instruments are acceptable for the test.
1981 and 1983 Type B and C Testing 1 Introductory Description of Testing < During 1981 and 1983 refueling outages, Type B and C primary containment leak rate testing was conducted in accordance with 10 CFR 50, Appendix J. Type B leakage tests were performed on containment penetrations utilizing gasketed seals prior to opening. This provided accurate as-found leakage data from the previous operating cycle. After each containment penetration closeout, a type B leak test was again performed. This leakage was combined with all measured leakage of the various containment isolation valves as a baseline for the upcoming operating cycle. The summary test results for type B penetrations are presented in Tables 81-B and 83-B. Type C leakage tests were performed on containment isolation valves. Four types of leakage tests were used, 1) the water leakage method, 2) the pressure drop method, 3) the pressure buildup method, and 4) the inleakage test method. All valves that were found to have leakage rates in excess of that allowed by the Technical Specifications were reported to the Director of the Office of Inspection and Enforcement, Regica 1, in thirty-day licensee event reports, LER 81-32 and 83-10. Following disassembly, repair, and retesting, a satisfactory leakage rate was demonstrated. The summary for Type C valves is presented in Tables 81-C and 83-C. MSIV leakages shown in these tables have been corrected to the equivalent 44 psig leakage to allow them to be included in the total. Due to maintenance requirements, some valves / penetrations were tested outside the refueling outages. The results of these tests are included as Table D. Valves That Exceeded the Leakage Criteria
- 1. Tech. Spec. Isolation Valves During the 1981 refueling outage, two primary containment isolation valves were found to have seat leakages in excess of that permitted by the Technical Specifications. On all valves found to have leakage greater than that allowed, a second valve on the same line provided the proper containment isolation capability. Testing, repair, and retest details for the valves found to have excessive leakage are described below.
a) Reactor Cleanup Suction Isolation Valve On October 23, 1981, the Reactor Cleanup Suction Isolation Valves, RCU-15 was leak tested and the test volume could not be pressurized. Disassembly and inspection of the valve revealed damage to the valve gate. The valve gate and stem were replaced and the valve was reassembled. Following the repair, the valve was retested and the leakage rate was found to be 0.0 lbm/hr. RCU-15 is a 4", 1500 lb motor operated gate valve manufactured by Wm. Powell Co.
i i b) Reactor Cleanup Return Isolation Valve L On November 11, 1981 the Reactor Cleanup Return i Isolation Valve, RCU-68 was leak tested and the test volume could not be pressurized. Disassembly and inspection of the valve revealed damage to the valve disc. The disc was replaced and the valve was re-assembled. Following the repair, the valve was retested and the leakage rate was found to be 0.048 lbm/hr. RCU-68 is a 4", 1500 lb motor operated globe valve manu-factured by Wm. Powell Co. During the 1983 refueling outage there were no valves listed in our Technical Specifications found to have excessive leakage. 1 4 2. Non-Tech. Spec. Isolation Valves During the 1981 refueling outage there were two valves tested which were determined to have excessive leakage. These valves are included in our leak test program but are not required to be tested by our Technical Specifications. The two valves are in series; however, this penetration is isolated by. manual valves during operation. SB-16-19-51 and 52 were tested on November 5, 1981 and were found to be leaking at a rate of 1.525 lbm/hr. Dis-assembly and inspection revealed the valve internals to be dirty. The valve internals were cleaned and the valves were reassembled. After repair, the leakage rate was found to be l 0.466 1hm/hr. SB-16-19-51 and 52 are 2", 600 lb. lift check ! valves manufactured by Hancock Co. i
- ' 'During the 1983 refueling outage there was one valve tested (FDW-96A) which was determined to have excessive leakage.
i This valve is included in our leak test program but is not re-l quired to be tested by our Technical Specifications. The upstream i valve (FDW-28A) is listed in our Tech. Spec. as a containment isolation valve not subject to type C testing. FDW-28A is there-fore assumed to be leaking the maximum allowable by our Technical Specifications, 0.522 lbm/hr. l t FDW 96A was tested on March 24, 1983 and found to be l leaking at a rate of 12.265 lbm/hr. Disassembly and inspection revealed damage to the resilient seat ring in the valve. The l seat ring was replaced and the valve was reassembled. After repair, the leakage was found to be 0.039 lbm/hr. FDW 96A is ! a 16" 900 lb. swing check valve manufactured by Anchor / Darling Valve Co. 1
Quantitive Calculations of Technical Specifications Limits ~
- 1. The combined leak rate of all penetrations and valves subject to Type B and C tests shall be less than 0.60 La. Sixty (60) percent of LA = - 354 lbm/ day.
- 2. The leakage from any one isolation valve shall not exceed 5% of Ltm. Five (5) percent of Ltm = 0.522 lbm/hr.
- 3. The leakage from any one main steam line isolation valve shall not exceed 11.5 SCFH at 24 PSIG (Pt).
General Conclusion Based on the successful completion of the Type A, B, and C leak rate test programs, along with the corrective action taken as a result of the test data, it is concluded that the condition of the Primary i Containment System is acceptable for continued plant operation. The plant was returned to service with a containment leakage of less than 0.318 WT%/ day. This compares to the allowed leakage of 0.600 WT%/ day. 4 1
% w.-~ -r- , sy---- _ ----- .-____%. . . , - -- , . , - , . - _ - -_ _,,,-_.-c ,.y. ,-,,,,.,_,,--,my , ,m._, ---
s 1 l AIR SUPPLY SCllDfATIC \J
---_____ ._._ _ _ _ q N,
Air Purge Supply l } d X V-16-19-9 C b, 900cfm VNP-10'1 Receiver
~~
Drywell FCV 3 y l , 1-156-10 d i V-16-l'. -8 FT-1-156-2 Air Compressors i N Bulk Storage Tank TI-1-156-9 2 l
- Disconnecting a fitting on FT-1-156-2 following
- Isolation and depressur-l ization of charging iine l I provides required vent l V-16-19-23 path Torus l V-16-19-10 I I I I
I I Reactor Building L ___ Figure I
N
. i i '
- I t i . !
l { - l t! -- +!. 7.
- e i i _!
- i[
- i . E N
}. :
t
.. : . _p t_ -
, i s 'L e
j-
-j- ,
)g l '
L.
; b.. _
. .. . I_. '
i '. y
,.3
'a
. j. y g
. _ d ... ...L. i.h __. -.;.._ _a_____",_ _q..._ 4 f -
i_. ;- - - . _ . E
- 9 l- ! ::;- - "
i
! c i
. y .
-:g-, :'
.m
- i. 3- .s s! y
_ %; .! _- [
. t... .
, , j ,, ,,y _._ ;, . ,, b*
g f: l. [- i .'j.i if- j i: [.
*g ...: % N 1 4 .
i , 4 l # . 5
- - : b. -_ ,.f
_a.
- 7. _+_ ",
. _.t_ ._ . _ .t ._ -- _.
- (
2 g . 1- . d. .-
- .!. ," l
- r , , i 4 g;
; D _i. .l l ! : i: *
.j ! i. l
. j- ._L__ . j___ .___p . : _j - ;, _ :_ _;_.. .._p_.. _ .4. - -.r-- __.1- 2-
.],j j _.}. :;- -l :1 :.- . , l . . .
g= ii e
--l...m
_A . : . - - . . .; ..- ., . _' j_ __ __L . _ , ._ . _ , _ , _;.;;, _ g
.y .-j.
.ij.
2- 2
- i. (mN i-
- :li-
]/ _
i :lE Y. y y
. tJ ;
- 1 -
-l-- ,; {- -y_ , . .
- ,3 g
_ . _ _ _ ._ m .i . i _ _ _ __.
-t-t !
i i
* .. *g
-[ : : . 7 ' , ,_.
.. i ;; j p '
i] .- . 1
'j r
.- .:: .;;. =- .; ...- O=
e
.:i !.in-
, . i. ,
. j': 4.. -
'I
,' Li s. _;. . _.
x.ij i_. f4_ _j_.. _.i j_ i.f a_. -_ h 2._-i - - ..S[il - - 3f n
- j:.: . . f_: . . : v3, : n. :i. :
- :- l:j- . [:
- . l .
- 1; r .-.l:-- '
-l-
.:l.. -
yo , ,44
; . j:: n:}n .f! .]i. , "- * ' ~
; { .
.l- ., - r !. . i .
3 jfgi
~' '
-- j.I' :;f:l [:' ' :i
'.:.f. ' f -l:, i:: : f; 6..
; fA: :
.] -
s. li: i [:_i'
.1: ; 1. .
- lf f!' [ <t w T.
gg :-
. h. : :: :C :- .m . :1 - . .
- : h'-j.
.. i; :. . }. : J :::.. . . . . .. +
u'"
- -(( i:!:y :- iij.i I
e:
. I [. i.j:t ~ .
i.f:l' Q! 3 rg
?i- ..d ._.
._ . _ . _ .. _ _ ~ ~. ! h k kii .
. I .I..- I'!'
~
i -.i.--
.. - - - . " +I.'.i _. 'h
-_.__+b._'.
_ .+._--
.__.4.
- 1....
- _?= ~-.:. .:;.
.. 7:. .:::
;.. 4 n 1, ..
..p. ~.-.{. : + M. "
- g. -.-
.: 7 n 3" 4
M id. _ l.fi- I!! :f'.
- l . -. :i. iihi I
- h. - .
~ _ _ .;.
_;;k:*::
~
.g i: ' !]:f' F f. iQi . !!" hi iiE 4 _ .I-~-
t i ?
!b N
- .3 hi :.. . t i.j:: if- . ni:: -i.. .:+
Mfi -,-. ::l: . *
- ii: i:f'i i:fii "
- !=n ' -=t=-W == x -. :2: '-
. ::: an- =l::: E r =- =i :E ;E --
--i =- =ij"'!= = t=" ""+
" H. : T h. ! iiE i:}2 'hi -' M. : ::lti *
-l:i i:l:i NT ele :- l'? iit
-~~
" I :. .' I i r !!tik .. Iib! .. !N $b -
I!!fif
^
+.._
+
l 5I5 i !b . .,,h.a $if!! 5 - INE !!! !! !! ! !N fh! ^
! !! o nl:: :.i r : i-i : 2.": fi 2:i:i-- iiht : !! -
.:I : di
~
p- "f"!:"- "
.]g[ E;l;[ . 2 [- ;((u: -% M---h [_ R9 I ."-- .
n; nf~
- f:
-t: :.tr :C '
_r t --- : 1:- -
~
ti. .b - 4... H iiin ; nF: : si:t .. hi.- i 3 si4 !i!!! 8
. . f-- r. .i..
ph. : i:.. rjn t
. : :'[:: _
, :-j:- :
-'[:-
- }g Eiii. .f'.
! iiiF_ !!..
~,
- i: t--
t i.. t . I
'7. L
-3.-. q-t ni-
-p ::7.
- .: I.'.--
r-iii : :.i.: ' j': :f.j- - i':
"H "9 t . . .i- l. i 6
-j- - h"- .j9 : f..
9.-- ---j"'
.M.-5.1!i "--
g t.. y.t-- f :-
.t- H i- '
i f. [h:E j t-
+"i "f ' :
2 hN
..b. id?..
i _hfh! !'.
.- ' M-i,. $~ !'
-. : 2!'i.-
-t
- J::
..^
T
..[-;
.t-3:- DE M
- .'- ' j.. 4
.:{::. -* .
6 +
-!- 1 -l: :9~ . . . .:
; t;2. .u; -, _ __ _
[_ _{ --_ L.L __.---.;a__ - - . . -
._.J---.}_ L_ ~ j.._ 4_ .- .h un: .j:7
- l.: ,[ , .
-l :
! ...: :it :-- .
- f-n=*
- 1. .._:! __.._ ._.:._. .a.:_ ....."
'{_ a . . -L . j . a..- - - - . ___{' +' t
; .s .p j .;
l - i
, . : .j. ':. ' g l: = -
.. n
; ' _. k. :._l u. ! t- ..!.-.
__..;... . . __ _._ f . ..
.a L_ i_
7- . ___.. . . . _p' - - . _ . . ._ . ja .
-i . ! , . ..
- n
! l * , l '
! , I-f ! !
.' e
. a : :.*- . . .
j t 1 l
- I i ,
' +
- I 4...,._.
., [ ..p i . .
[ e { . j- .
~
m i- l- p
._ ' f l
- f f. i l l n
o O O O n 2 m NN u ea u g b N N, N H O P g ( Otti LP g e - . enu .mwm ..ey .. ya . .Al , g ( i
. ! _ .. -y'.-_._. r
. - '_L.-..- -.3 I
---.+
l
;..- + -
, t y, l i i 2-
! l ! O g
i ,. , c
, . ,. es
.. b] . . t a i .
i j.
. _ . . . _ A. . .-.J-. 41 --4 _R - - . - - - -
; 3--. - -
- --- g
- R' , i i ,
(- t - 0 j . ]_;. . .. . - . . - [ - --
. i. : l , N
. t. . la I i . i e.
. . - -- ~ . . . - _ * - - -
-g ,
---t i
g- - + - -
- - ; ,O g, I
I n _i: w*e
' , N u , %
j _.ig! g
. .L ;. . .._L.... ..d l l . -.j. ;r. >if
- -. i j
- - ..L---
-5 JL f-- -- - -+--
BE N. --e. ., ! 1, ;
.t. --
.e c- g
- K i- ". :i * ' {
_ g. K . . p . . - . ---1--. ---y'.-. "i
. a. 4 R-.
4 i
--{--- - [ ~~ ---?H-.--
=
t'l-i - _l z i
']
g
. . !. . :.. . ::l.: -
.+-
t t-
!g=
y
. a, n1 .
m , e . 4
- i. ..3
_ ;_2 .mm.,.,
+L.. 4 -
--j- .i---.
- y-,- -- - - - "- -. ,
I
-=>
.,, t.: .,
j: .l-
~ f- :, 7.l,,
g g
~ ,
t * ,s ;.. .
.. ,..-. ; j:. : . -
4 g-.. =. e ,a,
..n.j_ ..
- p g:
' {i .-
_.u_ g l .1j a -.j--. . J---- -- :i J- --t-- -l^ 7.t :. . y
- .t. ..,[ .
- l :- .l- -{- -t.. is i ..!-.
7,J
- .
- 4
- . . .... e : j--. . 1.- ,,=
- g! :
_ _ ;.^~ ._ .e;;;. t. 21 -
- .:. .:-- f ... - _ , . :["
a t- , ::!:.
.*{.'
~
t .
?
- g. ; .
. ii.i.i U g
- j. ! ^ {L .l- ! *
' t 2 (N
, , ' =* N
% .j,
.; . u. r{. . .g ..-. .e 22 '
._:-_ u}- . p_. = rh: . g- . u.
-J. .:!..~
- + n Er. =.. 't---
--l:- .-
;r . h:- 2=.
. .e . .. 1. . z. .
, t.
- I. ::. t. : . :
p m
- e. s *
[
. . b; '*
- 3: :p: w * ;:g-
..e.d: . 2 R-" E- .'
[ L-y- L- . C
.. " r. . '
'un -
n **': - . .t:' g : h- : 'fi -
- s- i
- g jJ
. ;_.- .za -
i.n :g= i::
- g -
~
xx"-
- "i
.@i- - -
+
-[i. g fiji :@i 7
. n
.Nfd
.t. ~.'- --l- w -
. _ , . ,'!M '
.. - .- -- s ;,._' &.. "..'-t'-
a y
..b;3 I![E 5" hi
. 'jM 'l'.
. . i-!!i.- ..., t ' !:E :: :'.
~~~" -- ~~ 8 I M M
" ;L :-
w- - t~'~-
]::U .x......g..
- {.: . : (- , in
- ~
"t= : I:- '
.g .
. 't :
- j :
r1- : t-- :','.
?) =. :- D ai . i in ::i ,
+: 4
..i:i; !"n '
_ A. . LJ . L
+
n!E . TH.
._et. ..._.
;: .$.,4 .; . .i. ;-~
_l.- n
.r :
- tx
-l:- r l '. :-
- . ln f --t- ! I g
~ ~ _1
= -
~
Lg.E .. 1 nr ~.- ~ % .t.
"-}+
6 g ut u. -
..t.- -
.e .,t . . - --n: . .e t. :..
J
-- I ...
--_.,. q
.x _ .
au .in c ' s. Q :.p; p.. _" - . . . . . 2 s 14 7 _.a 2
- ;-i 2- w-N "-
.I n$
k n;, ; 4- -r:"4";p ; . g h. IT~I~
- ;x y n. .. ) - ' " -
, rt- -
nr - + - r" : % .c - g w
- i
-8
- 5. :'p: -.
n gu=n k j:lj chEi "l;! 'ji ih HE i. 2i N!N '4
- . J,.u.
.:- ..n..
e nn: = ; x b . . . . . ... H E ". 3 . h.q - .-- !nx.-t.
.e t 4 .. .
=..1.. : . h. . ..:{n. . . _:ln.. . .r .:.
- - - - . t. n. -- n. ..
.. s r
- h%
niu utu . ix.- n =2= :. . .- -u au ---.a. ...: a a x.. . ni x. a_._. ..a.;__;.__::
- 22:.
. nix : .1.n .=;< ln : :. In:-- 2 m- a M :.
N un -- t-j- ,4 =- ;. : .-ii =iipi~
~
=. iq :
n!n- ., ; ,p.
=ra . f
=i -- - "-
4 ...: - y jg
, ; . .a " _
j .Qg} ", ;;n jp- ""9
$=
i:; _ g . --
# a.g_
ni -
. g== .'. ...
- - .n.- j. ,
4[-[ i...tii Bi
" :19 =? ie
'll -
I- t- + t r r-- - - ni
;. :4 A
- =-!-_
.- . . . g. .' .: . . . .
-r- . . .:{n rta
'~~~~- ;d -
_ag._:_ ._ :_2 . " +
+ un
.l . . . .. . 3 r :. :I:n.
r - . .u: :.[.. v- .- y
- i
~~ l - gn *., i.f. _n. ;nr
.=.
(. t. i
- .!!!J :
_2__pa_
;p -
rix yi -._' : : 5 ~ i:. ' iiiH : D
---w- = -. - -- . . ...
T :.!'- : j :' :. E ii ii: -= . . . .i- .- ~ i r!E X 6 1.'
-; -b % i
." ; . . . . .. - r. : ..'
_a_. := {... 4 . 1-t
.: .==@._ . . ! ..
.-t.. :-
g m. 22 =.
.x t
- x. ; ..
3 ,, t .
., r s.
3
. s - ,.
6 e 'I^' :;
.._.l._._.._-@..>-
- M: _ . . . f --H ?' -
9- -
+
- "i.
1 -
, vi
- -- e t
- 3, . a4-- Q . . l. i. '
M ,_,_2, ; g
. d i v. : n.
...(- }
- ..r
. j ,! [i _:. _ p_.4 }; - ---
.-- - -- - - - " * " ~ -- -- --'-~
. t-- M-n l
, , . ~ 1. -~. ~ .
I E'e t
~
t
,g. .
l _d .. . . . " b. .a__. _.r..- .L.-
.J- --
-,"" - - * - - - ~ ~ - ' " - ~~
, j - i. .J~~
I'
. 1,. -!
i = [
- l ,_2._. . _ . . . .;_. . .i -.L i--. ---4 - ! d ~~~ ' ~* * ' ' ' - "
' '- D
' ~ * ~ '
~ ~ - * ~ ~ ~ .~~ '~T~'~~~
.i i E, '
( _* ' k 2
, a
, e g % O %
n i s * ~ *
; 4 ny
' W % *er v
g ( CtZi it ( oms
..,.m..m.,w...
- m m a m -ay
PRIMARY CONTAISMENT LEAKAGE RATE DATA SHEET (TYPE A) r TABLE 1983A Time Contained- Pressure Temp. I Time Contained Pressure Temp. (Min) Mass (pounds) "Hg *F $ (Min) Mass (pounds) "Hg *F n?n1 71065.R59 119.839 89.9 0536 73002.646 119.568 89.6 n?1 a 71nA7.R56 119.823 89.9 $ 0547 72999.349 119.562 89.6 5 n??1 71057.6R1 119.807 89.9 $ 0557 72998.463 119.551 89.6 0233 73054.683 119.791 89.9 h 0607 72996.432 119.544 89.6 0244 73056.325 119.773 89.8 0617 72996.683 119.537 89.6 0254 73054.166 119.759 89.8 0627 72992.755 119.526 89.6 5 0304 73053.091 119.743 89.8
- 0637 72990.023 119.511 89.5 0314 73043.756 119,729 89.8 0648 72986.073 119.507 89.5 0324 73044.271 119.715 89.8 0658 72988.716 119.499 89.5 a
0335 73039.662 119.696 89.7
- 0708 72982.122 119.491 89.5
(.' 0345 73037.504 119.682 89.7 i
- 0718 72985.433 119.485 89.5 0355 73035.809 119.670 89.7 0728 72980.103 119.480 39.5.
, 0405 73029.112 119.660 89.7 0739 72977.185 119.474 89.5 0415 73023.723 119.650 89.8 0749 72972.846 119.467 89.5 0425 73026.~/01 119.640 89.7 0759 72971.813 119.464 89.5 0435 73019.254 119.630 89.7 0809 72970.524 119.457 89.5 2 0446 73011.906 119.618 89.7
- 0819 72968.869 119.454 89.5 0456 73010.826 119.607 89.7 0830 72994.459 119.450 89.5 0506 73007.587 119.598 89.7 0840 73002.339 119.445 89.4 0516 73012.390 119.587 89.6 0850 72989.833 119.440 89.5 0526 73008.771 119.578 89.6 0900 72987.334 119.435 89.5 Test Asst. h
' N(k/ G/Y 0. $k' y Date /f-//-f3 Approved ./_
/
b VYOPF 4029.04 Rev. 1
PRIMARY CONTAIDIENT LEAKAGE RATE DATA SHEET (TYPE A) r n Time Contained Pressure Temp. 7 Time Containad Pressure Temp. (Min) Mass (pounds) "Hg *F g (Min) Mass (pounds) "Hg *F 0911 72999.622 119.431 89.4 k 1245 72964.367 119.409 89.7 0921 72996.001 119.426 89.4 k 1255 72972.489 119.409 89.6 0931 72987.224 119.421 89.5 h 1305 72962.768 119.407 89.7 0941 72991.972 119.417 89.4 k 1316 72969.089 119.405 89.7 0951 72989.067 119.415 89.4 k 1326 72967.730 119.404 89.7 1002 72986.805 119.411 89.4 h 1336 72967.250 119.402 89.7 1012 72984.193 119.408 89.5 k 1346 72963.277 119.400 89.7 1022 72991.336 119.407 89.4 h 1356 72963.727 119.399 89.7 1032 72992.269 119.407 89.4 k 1407 72968.371 119.397 89.7
~
1042 72983.176 119.406 89.4 h 1417 72966.628 119.396 89.7 (- 119.405 89.5 Z
- 1427 72968.270 119.395 89.7 1053 72982.728 1103 72990.896 119.403 89.5 k 1437 72968.270 119.395 89.7 1113 72989.901 119.405 89.5 k 1447 72968.775 119.394 89.7
,m 1123 72991.499 119.407 89.5
- 1458 72958.680 119.392 89.8 1133 72992.727 119.409 89.5 2 1508 72951.812 119.391 89.8 1144 72985.69 119.412 89.6
- 1518 72951.717 119.389 89.8
,a 1154 72986.921 119.414 89.6
- 1528 72951.344 119.389 89.8 72986.921 119.414 89.6
- 1538 72949.369 119.387 89.8 1204 .
t x 72985.560 119.413 89.6 k 1549 72948.811 119.387 89.8 1214 72o73,007 119.412 89.7
- 1559 72947.960 119.387 89.8
_ 1.224 c ! 1225 72967.579 119.410 89.7
- 1609 72947.960 119.385 89.8 Test Asst. $l//kGpf k 0((yff
\ \. Date l-//-/J ( Approved / f/ OP,f , - Test Coordinator 4 VYOPF 4029.04 ! Rav. 1 I
PRIMARY CONTAI!: MENT LEAKAGE RATE DATA SHEET (TYPE A) r TABLE 1983A sr Time Contained Pressure Temp. Time Contained Pressure Temp. (Min) Mass (pounds) "Hg *F (Min) Mass (pounds) "Hg 'F { 1619 72945.416 119.383 89.8 1954 72942.359 119.345 89.9 1630 72945.179 119.382 89.8
- 2004 72941.373 119.344 89.9 1640 72944.145 119.380 89.8 k 2014 72933.767 119.343 90.0 1650 72935.966 119.379 89.8 2024 72933.393 119.343 90.0 1700 72938.108 119.377 89.9 h 2035 72932.405 119.342 90.0 1710 72939.571 119.375 89.8 k 2045 72933.527 119.342 90i0 1721 72934.404 119.374 89.8 h 2055 72924.855 119.342 90.1 1731 72932.429 119.372 89.8 h 2105 72926.163 119.342 90.1 1741 72931.952 119.370 89.9 2115 72926.163 119.342 90.1 1751 72931.475 119.368 89.9 k* 2126 72916.311 119.341 90.2
(.- 1801 72930.995 119.366 89.9 % 2136 72916.963 119.339 90.2 1812 72924.504 119.364 89.9 % 2146 72915.462 119.339 90.2 1822 72928.276 119.364 89.9 $ 2156 72916.351 119.338 90.2 1832 72924.181 119.361 89.9 2, 2207 72921.655 119.338 90.2 90.2 1842 72923.710 119.359 89.9 f 2217 72913.246 119.336 1852 72923.473 119.358 89.9 $ 2227 72913.717 119.334 90.3 1903 72921.258 119.355 89.9 2237 72911.879 119.331 90.3 1913 72947.130 119.354 89.9 k 2247 72909.292 119.328 90.3 1923 72941.667 119.350 89.9 % 2258 72906.702 119.325 90.3 1933 72936.272 119.348 89.9 $ 2308 72908.837 119.323 90.3 1933 72939.593 119.346 89.9 % 2318 72903.401 119.319 90.3 Test Asst. OM/ 4/ O , '2h
\. Date l if f- ?]
Approved // 8// , Test Coordinator VYOPF 4029.04 Rev. 1
t PRIMARY CONTAIEMENT LEAKAGE RATE DATA SHEET (TYPE A) r TABLE 1983A Time Contained Pressure Temp. 7 Time Contained Pressure Temp. (Min) Mass (pounds) "Hg *F $ (Min) Mass (pounds) "Hg *F 72902.312 119.316 90.3 73163.'9 119.647 90.0 2318 f0303 2339 72899.348 119.313 90.3
- 0313 73157.0 119.613 90.1 1
2349 72898.021 119.309 90.3 $ 0323 73128.9 119.595 90.0 2359 72894.719 119.303 90.3 $ 0333 73124.6 119.581 90.0 0009 72890.188 119.295 90.3 $ 0344 73127.2 119.569 89.9 7 0019 72883.130 119.285 90.3 $ 0030 72883.853 119.276 90.3 % 0040 72886.199 119.266 90.2 ,k 0050 72888.385 119.260 90.1 { 72886.066 119.255 90.1 % (.~0100 0110 72887.003 119.255 90.1 k 7 0121 72885.454 119.254 90.1 { 0131 72887.262 119.253 90.1 $" 0141 72884.489 119.250 90.1 h 0151 72872.771 119.245 90.2 $" 0202* 72868.154 119.239 90.2 % 0212 72862.875 119.231 90.2 { 0222 72868.433 119.225 90.2 % 0232 72869.151 119.216 90.1 % 0242 72862.2 119.209 90.1 { 0253** 72926.3 119.270 90.1 { Test Asst. 0l2' b'27W 0 'Y$h
- End of 24-hour test.
\- Date l~/AP3 ** Supplemental Test pumpback completed at 0300.
Approved [/ /[y , VYOPF 4029.04 Test Coordinator Rev. 1
Summary Test Results for Type B Testing Table 81-B PENETRATION LEAKAGE (LBM/HR) NUHBER DESCRIPTION INITIAL RETEST X-2 Personnel Lock 1.720 1.720 Bellows Seals X-7A Main Steam Line A 0.000 X:-7B Ma in Steam Line B 0.000 X-7C Main Steam Line C 0.000 X-7D Main Steam Line D 0.000 X-9A Feedwater A 0.000 X-9B Feedwater B 0.000 X-ll HPCI Steam Line 0.000 X-12 RHR Suction 0.000 X-13A RHR Return A 0.000 X-13B RHR Return B 0.000 X-14 Cleanup Suction 0.000 X-16A Core Spray A 0.000 X-16B Core Spray B 0.000 Electrical Penetrations 100A Electrical Penetration 0.000 100B Electrical Penetration 0.001 100C Electrical Penetration 0.000 100D Electrical Penetration 0.000 101A Electrical Penetration 0.000 101C Electrical Penetration 0.003 101D Electrical Penetration 0.001 102 Electrical Penetration 0.000 l l l
Table 81-B (Cont'd) Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST 103 Electrical Penetration 0.000 104A Electrical Penetration 0.000 104B Electrical Penetration 0.000 104C Electrical Penetration 0.001 105A Electrical Penetration 0.000 105B Electrical Penetration 0.000 105C Electrical Penetration 0.000 105D Electrical Penetration 0.000 214 Electrical Penetration 0.000 Double Gasketed Seals X-1 Equipment Hatch 0.002 X-4 Drywell Head Access Hatch 0.000 X-6 Control Rod Drive Removal 0.000 0.000 Hatch X-200A Torus Access Hatch 0.000 X-200B Torus Access Hatch 0.000 0.000 VBC-A Vacuum Breaker Access Cover 0.000 0.001 VBC-B Vacuum Breaker Access Cover 0.000 0.002 VBC-C Vacuum Breaker Access Cover 0.000 VBC-D Vacuum Breaker Access Cover 0.000 VBC-E Vacuum Breaker Access Cover 0.000 VBC-F Vacuum Breaker Access Cover 0.000 VBC-G Vacuum Breaker Access Cover 0.000 VBC-H Vacuum Breaker Access Cover 0.000 VBC-I Vacuum Breaker Access Cover 0.000 VBC-J Vacuum Breaker Access Cover 0.000
l Table 81-B ' (Cont'd) Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST VBSL-A Vacuum Breaker Shaft Left -0.000 VBSR-A Vacuum Breaker Shaft Right 0.000 VBSL-B Vacuum Breaker Shaft Left 0.000 VBSR-B Vacuum Breaker Shaft Right 0.000 VBSL-C Vacuum Breaker Shaft Left 0.000 VBSR-C Vacuum Breaker Shaf t Right 0.000 VBSL-D Vacuum Breaker Shaft Left 0.000 VBSR-D Vacuum Breaker Shaft Right 0.000 VBSL-E Vacuum Breaker Shaft Left 0.000 VBSR-E Vacuum Breaker Shaft Right 0.000 VBSL-F Vacuum Breaker Shaft Left 0.000 VBSR-F Vacuum Breaker Shaft Right 0.000 VBSL-G Vacuum Breaker Shaft Left 0.000
-VBSR-G Vacuum Breaker Shaft Right 0.000 VBSL-H Vacuum Breaker Shaft Left 0.000 VBSR-H Vacuum Breaker Shaft Right 0.000 VBSL-I Vacuum Breaker Shaft Left 0.000 VBSR-I Vacuum Breaker Shaft Right 0.000 VBSL-J Vacuum Breaker Shaft Lef t 0.001 VBSR-J Vacuum Breaker Shaft Right 0.000 SLH-A Shear Lug Access Cover 0.004 SLH-B Shear Lug Access Cover 0.000 SLH-C- Shear Lug Access Cover 0.000 SLH-D Shear Lug Access Cover 0.000 SLH-E Shear Lug Access Cover 0.002 SLH-F Shear Lug Access Cover 0,000 SLH-G Shear Lug Access Cover 0.002 SLH-H Shear Lug Access Cover 0.000 Drywell Head Flange 0.027 0.001 X-213-A Torus Drain 0.000 X-213-B Torus Drain 0.000 X-35A TIP Penetration Flange 0.000 X-35B TIP Penetration Flange 0.000 X-35C TIP Penetration Flange 0.000 i
X-35E -TIP Penetration Flange 0.000 Total-B Penetration Leakage After Repairs 1.741
Summary Test Results for Type C Testing Table 81-C LEAKAGE (LBM/HR) DESCRIPTION INITIAL RETEST VALVE (S) TESTED MS-77 Main Steam Drain 0.113 RV39 & 40 Recire. Sample 0.009 RHR-57 RHR Disch. to Radwaste 0.047 LRW-83 Drywell Floor Drain 0.379 LRW-95 Drywell Equip. Drain 0.478 SB-16-19-8,9,10 & 23 Containment Purge 0.000 0.369 SB-16-19-11A & 12A Vacuum Relief 0.015 SB-16-19-11B & 12B Vacuum Relief 0.124 SB-16-19-6,7,6A,6B,7A Containment Exhaust 0.830 and 7B RCU-18 Reactor Cleanup 0.009 V-16-20-20 Containment Purge Makeup 0.010 0.015 V-16-20-22A Containment Purge Makeup 0.028 0.011 V-16-20-22B Containment Purge Makeup 0.006 0.010 RCU-68 and CRD-181 Reactor Cleanup could not seat 0.477 IIPCI-16 HPCI Steam Supply 0.107 RCIC-16 RCIC Steam Supply 0.038 CA-38A Cont. Air Compressor 5,0.096 CA-38B Cont. Air Compressor 5.0.096 Suction CA-89B Instrument Air Check Valve 0.002 CA-89C Instrument Air Check Valve 0.003 NG 13A & 13B, 15 CAD Injection 0.010 NG 12A & 12B CAD Injection 0.005 NG llA & 11B CAD Injection 0.025 VG-9A CAD Vent 0.012 VG-22A CAD Vent 0.045 VG-9B CAD Vent 0.019 c
Table 81-C (Cont'd) Summary Test Results for Type C Testing LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST VG-22B CAD Vent 0.014 VG-23 CAD Rad. Mon. Supply 0.021 VG-26 CAD Rad. Mon. Supply 0.015 VG-76A Rad. Mon. Return 0.105 VG-76B Rad. Mon. Return 0.003 MS-74 Main Steam Drain 0.000 0.113 HPCI-15 HPCI Steam Supply 0.000 0.107 RCIC-15 RCIC Steam Supply 0.000 0.038 RCU-15 Reactor Cleanup could not seat 0.000 LRW-82 Drywell Floor Drain 0.131 LRW-94 Drywell Equipment Drain 0.075 RHR-66 RHR Discharge to Radwaste 0.000 RHR 29/32 Head Spray Line 0.000 0.006 corrected RHR 33 Head Spray Line 0.006 FDW-7A,7B,37A,37B, 5 Feedwater 1.524 SB-16-19-51/52 PCAC 1.525 0.466 SB-16-19-53 PCAC 0.042 IA-103 Instrument Air Check Valve 0.013 FDW-27A . Feedwater Check Valve 0.002 FDW-96A Feedwater Check Valve 0.008 MS80A A Main Steam Line 0.187 MS86A A Main Steam Line 0.503 MS80B B Main Steam Line 0.049 MS86B B Main Steam Line 0.318 MS80C C Main Steam Line 0.000 MS86C C Main Steam Line 0.265 MS80D D Main Steam Line 0.000 MS86D D Main Steam Line 0.106 Total Type C Leakage Following Repairs 7.461 l Total Type B & C Leakage Following Repairs 9.202 l Summary Test Results for Type B Testing Table 83-B PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST X-2 Personnel Lock 0.574 lbm/hr 1.461 Bellows Seals X-7A Main Steam Line A 0.000 X-7B Main Steam Line B 0.000 X-7C Main Steam Line C 0.000 X-7D Main Steam Line D 0.000 X-9A Feedwater A 0.000 X-9B Feedwater B 0.000 X-ll HPCI Steam Line 0.000 X-12 RHR Suction 0.000 X-13A RHR Return A 0.000 X-13B RHR Return B 0.000 X-14 Cleanup Suction 0.000 X-16A Core Spray A 0.000 X-16B Core Spray B 0.000 Electrical Penetrations 100A Electrical Penetration 0.000 100B Electrical Penetration 0.000 100C Electrical Penetration 0.001 100D Electrical Penetration 0.000 101A Electrical Penetration 0.001 101C Electrical Penetration 0.045 101D Electrical Penetration 0.000 102 Electrical Penetration 0.008 1
- l
)
Table 83-B (Cont'd) Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST 103 Electrical Penetration 0.002 104A Electrical Penetration 0.000 104B Electrical Penetration 0.001 104C Electrical Penetration 0.000 105A Electrical Penetration 0.000 105B Electrical Penetration 0.001 105C Electrical Penetration 0.000 105D Electrical Penetration 0.004 214 Electrical Penetration 0.000 Double Gasketed Seals t X-1 Equipment Hatch 0.001 X-4 Drywell Head Access Hatch 0.000 X-6 Control Rod Drive Removal 0.000 Hatch X-200A Torus Access Hatch 0.000 0.000 X-200B Torus Access Hatch 0.000 0.000 VBC-A Vacuum Breaker Access Cover 0.000 0.000 VBC-B Vacuum Breaker Access Cover 0.203 0.000 VBC-C Vacuum Breaker Access Cover 0.000 0.000 VBC-D Vacuum Breaker Access Cover 0.000 0.000 VBC-E Vacuum Breaker Access Cover 0.000 0.000 VBC-F Vacuum Breaker Access Cover 0.000 0.000 VBC-G Vacuum Breaker Access Cover 0.000 0.000 VBC-H Vacuum Breaker Access Cover 0.000 0.000 VBC-1 Vacuum Breaker Access Cover 0.000 0.000 VBC-J Vacuum Breaker Access Cover 0.000 0.000 f
Table 83-B (Cont'd) Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST VBSL-A Vacuum Breaker Shaft Left 0.000 VBSR-A Vacuum Breaker Shaft Right 0.000 VBSL-B Vacuum Breaker Shaft Left 0.000 VBSR-B Vacuum Breaker Shaft Right 0.000 VBSL-C Vacuum Breaker Shaft Left 0.000 VBS R-C Vacuum Breaker Shaft Right 0.000 VBSL-D Vacuum Breaker Shaft Left 0.000 VBSR-D Vacuum Breaker Shaft Right 0.000 VBSL-E Vacuum Breaker Shaft Left 0.000 VBSR-E Vacuum Breaker Shaft Right 0.000 VBSL-F Vacuum Breaker Shaft Left 0.000 VBSR-F Vacuum Breaker Shaft Right 0.000 VBSL-G Vacuum Breaker Shaft Left 0.000 VbSR-G Vacuum Breaker Shaft Right 0.000 VBSL-H Vacuum Breaker Shaf t Left 0.000 VBSR-H Vacuum Breaker Shaft Right 0.000 VBSL-I Vacuum Breaker Shaft Left 0.000 VBSR-I Vacuum Breaker Shaft Right 0.000 VBSL-J Vacuum Breaker Shaft Left 0.000 VBSR-J Vacuum Breaker Shaft Right 0.000 SLH-A Shear Lug Access Cover 0.000 SLH-B Shear Lug Access Cover 0.000 SLH-C Shear Lug Access Cover 0.000 SLH-D Shear Lug Access Cover 0.000 SLH-E Shear Lug Access Cover 0.002 SLH-F Shear Lug Access Cover 0.000 SLH-G Shear Lug Access Cover 0.002 SLH-H Shear Lug Access Cover 0.000 Drywell Head Flange 0.014 X-213-A Torus Drain 0.000 X-213-B Torus Drain 0.000 X-35A TIP Penetration Flange 0.000 X-35B TIP Penetration Flange 0.000 X-35C TlP Penetration Flange 0.000 X-35E TIP Penetration Flange 0.000 Total B Penetration Leakage After Repairs 1.543
~
Summary Test Results for Type C Testing Table 83-C LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS-77 Main Steam Drain 0.326 RV39 & 40 Recire. Sample 0.018 RHR-57 RHR Disch. to Radwaste 0.051 LRW-83 Drywell Floor Drain 0.418 LRW-95 Drywell Equip. Drain 0.042 SB-16-19-8,9,10 & 23 Containment Purge 0.113 SB-16-19-11A & 12A Vacuum Relief 0.037 SB-16-19-11B & 12B Vacuum Relief 0.126 SB-16-19-6,7,6A,6B,7A Containment Exhaust 0.489 and 7B RCU-18 Reactor Cleanup 0.034 V-16-20-20 Containment Purge Makeup 0.001 V-16-20-22A Containment Purge Makeup 0.001 V-16-20-22B Containment Purge Makeup 0.015
,RCU-68 and CRD-181 Reactor Cleanup 0.182 0.386 HPCI-16 HPCI Steam Supply 0.043 RCIC-16 RCIC Steam Supply 0.477 CA-38A Cont. Air Compressor 0.181 CA-38B Cont. Air Compressor 0.017 Suction CA-89B Instrument Air Check Valve 0.018 CA-89C Instrument Air Check Valve 0.027 NG 13A & 13B, CAD Injection 0.001 NG 12A & 12B CAD Injection 0.001 NG llA & llB CAD Injection 0.001 VG-9A CAD Vent 0.001 VG-22A CAD Vent 0.001 VG-9B CAD Vent 0.001
Table 83-C (Cont'd) Summary Test Results for Type C Testing LEAKAGE (LBM/HR) DESCRIPTION INITIAL RETEST VALVE (S) TESTED VG-22B CAD Vent 0.034 VG-23 CAD Rad. Mon. Supply 0.001 VG-26 CAD Rad. Non. Supply 0.001 VG-76A Rad. Mon. Return 0.001 VG-76B Rad. Mon. Return 0.001 MS-74 Main Steam Drain 0.004 HPCI-15 HPCI Steam Supply 0.000 RCIC-15 RCIC Steam Supply 0.000 RCU-15 Reactor Cleanup 0.032 LRW-82 Drywell Floor Drain 0.025 LRW-94 Drywell Equipment Drain 0.027 RHR-66 RHK Discharge to Radwaste 0.000 SB-16-19-51 PCAC 0.067 SB-16-19-52 PCAC 0.015 1A-103 Instrument Air Check Valve 0.025 FDW-27A Feedwater Check Valve 0.096 FDW-96A Feedwater Check Valve 12.265 0.039 CRD-413B Recirc Pump Seal Purge ISO 0.021 Valves (check) CRD-413A Recirc Pump Seal Purge 0.045 ISO Valves (Check) CRD-412A Recire Pump Seal Purge 0.001 ISO Valves (check) CRD-412B Recirc Pump Seal Purge 0.039 ISO Valves (check) PCV2-32A North SDV Vent 0.023 PVC3-32B South SDV Vent 0.013 LCV3-33A North SDV Drain 0.001 LCV3-33B South SDV Drain 0.182 IfV3-33C North SDV Drain 0.027 LCV3-33D South SDV Drain 0.001 CRD-162A North SDV Vent 0.030 CRD-162B South SDV Vent 0.012 k _ _ - - _ _ - - _ _ _ _
Table 83-C (Cont'd) Summary Test Results for Type C Testing LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS80A A Main Steam Line 0.386 MS86A A Main Steam Line 0.933 MS80B B Main Steam Line 0.000 MS86B B Main Steam Line 0.373 MS80C C Main Steam Line 0.000 MS86C C Main Steam Line 1.065 MS80D D Main Steam Line 0.000 MS86D D Main Steam Line 0.277 Total Type C Leakage Following Repairs 6.623 Total Type B & C Leakage Following Repairs 8.166 k
TABLE D Leakage Test Performed Outside of Shutdown Type B Penetration Description Date Leakage (lbm/hr) X-2 Personnel Lock 10/16/81 1.720 X-2 Personnel Lock 9/1/82 0.430 X-2 Fersonnel Lock 1/11/83 0.000 X-2 Personnel Lock ,2/2/83 0.574 Type C Valve No. Description Date Leakage (1bm/hr) SB-16-19-8,9,10,23 Containment Purge 6/10/82 0.369 V-16-20-20 Containment Purge Makeup 6/22/82 0.015 V-16-20-22A Containment Purge Makeup 6/22/82 0.011 V-16-20-22B Containment Purge Makeup 6/22/82 0.010 V-16-20-20 Containment Purge Makeup 1/9/83 0.018 V-16-20-22B Containment Purge Makeup 1/9/83 0.025 V-16-20-20 Containment Purge Makeup 2/15/83 0.004 V-16-20-22B Containment Purge Makeup 2/15/83 0.011
VERMONT YANKEE NUCLEAR POWER CORPORATION 2.C.2.1
. RD 5, Box 169. Ferry Road, Erattleboro, VT 05301 7, p' ENGINEERING OFFICE 1671 WORCESTER ROAD
- FRAMINGHAM, MASSACHUSETTS 01701 TELEPHONE 617 872-8100 September 13, 1983 U,S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Office of Nuclear Reactor Regulation Harold R. Denton, Director
Reference:
(a) License No. DPR-28 (Docket No. 50-271)
Dear Sir:
Subject:
Primary Containment Leak Rate Test Report In accordance with the requirements of Appendix J to 10 CFR 50, we hereby submit a copy of the report entitle'd, " Vermont Yankee Primary Containment Leak Rate Test 1983." We trust this information is acceptable to you; however, should you have any questions, please contact us. Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION h Warren P. rphy TV Vice Presi ent and Manager of Operations WPM /dm J l0IY t}}