NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant
| ML20210T240 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/09/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210T237 | List: |
| References | |
| RTR-NUREG-1482 GL-89-04, NUDOCS 9908190037 | |
| Download: ML20210T240 (10) | |
Text
.
g gg i UNITED STATES g
o
,j NUCLEAR REGULATORY COMMISSION A" WASHINGTON, D.C. 20seHoci
%...../ ,
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE TESTING PROGRAM. SECOND TEN-YEAR INTERVAL FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT j DOCKET NUMBER 50-440
1.0 INTRODUCTION
1 The Code of Federal Regulations,10 CFR 50.55a, requires that inservice testing (IST) of certain ASME Code Class 1,2, and 3 pumps and valves are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (the Code) and applicable addenda, except 1 where attematives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to Sections (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a.
In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed altematives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for its facility. NRC guidance contained in Generic Letter (GL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs", provides attematives to the Code requirements determined to be acceptable to the staff. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants." Attematives that conform with the guidance in GL 89-04 may be implemented prior to receiving NRC approval, but should be included as relief requests for review by the staff. When attematives are implemented in accordance with the relevant position in the generic letter, the staff has determined that relief should be granted pursuant to 10 CFR l 50.55a(f)(6)(i) on the grounds that it is authorized by law, will not endanger life or property or the ;
common defense and security, and is otherwise in the public interest. In making this !
determination, the staff considers the burden on the licensee that would result if the requirements were imposed. ;
Section 10 CFR 50.55a authorizes the Commission to approve attematives and to grant relief from ASME Code requirements upon making the necessary findings. The NRC staff's findings with respect to authorizing attematives and granting or not granting the relief requested as part of the licensee's IST program are' contained in this safety evaluation (SE).
FirstEnergy (the licensee) based the Perry IST program on the requirements of the 1989 Edition of ASME Section XI, Subsections IWP and IWV, which is incorporated by reference in 10 CFR 50.55a. ASME Operations and Maintenance (OM) Standard Part 6, for IST of pumps is referenced by Subsection IWP and OM Standard, Part 10, for IST of valves is referenced by Subsection IWV. The relief requests were reviewed against the requirements of the 1989 Enclosure 9908190037 990009 PDR ADOCK 05000440 P PM ,
2 Edition of ASME Section XI for pumps and valves. A summary of NRC's action on each relief request is provided in Attachment 1.
The test deferrals for valves which are in accordance with Part 10 have been reviewed and are summarized in Tables A.1 and A.2 of the Technical Evaluation Report (TER) which is included as Attachment 2 to this SE.
2.0 EVALUATION 2.1 Relief Reauests The Mechanical & Civil Engineering Branch, with technical assistance from BNL, has reviewed the information concoming IST program requests for relief submitted by the licensee for the second ten-year interval for Perry in a letter dated July 22,1998. The staff adopts the evaluations and recommendations for granting relief or authorizing attematives contained in the TER prepared by BNL.
For the Perry IST Program, relief is granted from, or attematives are authorized in lieu of, the testing requirements which have been determined to be impractical to perform, where an attemative provides an acceptable level of quality and safety, or where compliance would result in a hardship or unusual difficulty without a compensating increase in quality or safety. The staff has determined that:
- 1) With respect to Relief Requests (RR) PR-2, PR-3, PR-6, VR-6, VR-7, and VR-10 (limited to the Category A and AC valves which are not reactor coolant system (RCS) pressure isolation valves (PlVs)), the proposed attematives provide an acceptable level of quality and safety. Therefore, the proposed attematives are authorized pursuant to 10 CFR
- 50.55a(a)(3)(i).
- 2) With respect to RRs VR-4, VR-5 and VR-9, compliance with the Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, the proposed attematives are authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
- 3) With respect to RR VR-1, the requirements of the Code are impractical. Therefore, relief is granted pursuant to O CFR 50.55a(f)(6)(i). The relief granted is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest. In making this determination, the staff has considered the burden on the licensee if the requirements were imposed on the facility.
The following attematives have been authorized on an interim basis:
RRs PR-4 and PR-5 have been authorized for a period of 1 year pursuant to 10 CFR 50.55a(a)(3)(ii) in order to allow the licensee to commit to implementing a condition monitoring program for these pumps and to address concems regarding the treatment of individual pump vibration parameters.
m l
3-The following relief request has been denied: i
- 4) RR VR-8 was denied because the licensee has not described the specific hardship in l meeting the Code requirements. BNL stated that the licensee should review the scope of these components to determine if they are required to be included in their IST i program.
The following relief request has not been authorized:
- 5) The altemative proposed for Category A and AC valves in relief request VR-10 which are RCS PlVs is not authorized. As discussed in Attachment 3, you are encouraged to resubmit the proposed attemative and include risk information that would justify the extension of the test interval.
The following relief request has been withdrawn:
- 6) RR VR-2 was withdrawn as documented in Revision 4 to the Pump and Valve Inservice Testing Program Plan for the Perry Nuclear Power Plant. The Program Plan, which was effective November 18,1998, was submitted to the staff on June 10,1999.
' In addition to the relief requests described above, BNL recommended that relief be denied for j RR PR-1. While BNL acknowledged that the licensee appeared to be in compliance with !
GL 89-04, Position 8, the proposed attemative could result in a delay of 6 or 7 days to perform an analysis of the test results. BNL concluded that the Code requirements do not present a unique burden to the licensee. However, the staff discussed this issue with the licensee and concluded that the licensee's proceduralized actions by on-shift personnel are sufficient to meet i l the requirements of OM(6)-6.2. Separate analysis of pump data by IST personnel within 96
) hours is not required. Therefore, the staff has concluded that the licensee's actions are l sufficient and that relief is not required for RR PR-1.
BNL also recommended that relief was not required for RR VR-7 because a change to the 1999 edition of the OM Code will include an identical change and this change is a clarification of the current Code requirements. The guidance in NUREG-1482, Section 4.3.9, states that the use of code clarifications may be used without further NRC approval if they are determined to be clarifications only. The staff, however, does not fully agree with BNL's evaluation provided in l Section 3.7 of the attached TER. The staff does not agree that the Code change is a clarification although the staff does find the Code change to be technically adequate. In addition, the Code changes have not beten published at the time of issuance of this SE. In a l review of BNL's discussion in the TER, the staff has determined that the proposed attemative is ;
l authojzed pursuant to 10 CFR 50.55a(a)(3)(i) because the proposed changes provide an i acceAable level of quality and safety.
The granting of relief is based upon the fulfillment of any commitmer;ts made by the licensee in !
l its basis for each relief re Nest and the attematives proposed. Program changes involving new l or revised relief requests must be submitted to NRC for review. Program changes that add or delete components from the IST program may be periodically provided to NRC.
l a
l
I , , )
L The proposed alternatives in RR VR-6, PR-3 and PR-6, were authorized by the staff in a letter I dated March 31,1999, to support the licensee's refueling outage. RR VR-08 was denied in this l
letter.
2.2 C;' .Ted Test Justifications
- The test deferrals of valves, as allowed by OM-10, were reviewed as part of BNL's evaluation.
Results of the review are provided in Section 4 of the TER with recommendations for further review by the licensee for specdic deferrals. A complete listing of the deferred test justifications
' is included in Appendices A.1 and A.2 of the TER. Recommended actions for several of the deferred test justifications are included in Section 6.0 C of the TER. Results of the review of deferred test justifications do not necessarily constitute final approval and are subject to NRC inspection.
! 2.3 System Review BNL, using the Perry Opdated Final Safety Analysis Report, conducted a scope review of the reactor core isolation cooling, low pressure core spray, and emergency closed cooling systems against the requirements of Section XI and the regulations. The review revealed a numbe,' of 1 items that did not appear to be in compliance with the Code requirements (see Section 6.0 D of l
' the TER). The licensee should review these items, as well as other systems that might contain l similar issues, and revise their program and take any necessary actions as appropriate.
2.4 Relief Reauests in Accordance with NRC GL 89-04 i
l For any relief granted based on following the positions stated in GL 89-04, the staff (with technical assistance from BNL) has reviewed the information submitted by the licensee to determine whether the proposed attemative testing follows the relevant position in the generic l letter. Comments related to relief requests which the licensee states are in accordance with !
GL 89-04 are included in Section 6.0 B of the TER.
New or revised relief requests that meet the positions stated in GL 89-04, Attachment 1, must be !
submitted to NRC bet may be implemented prior to staff approval provided the guidance in i GL 89-04, Section D, is followed.
2.5 Action items f-
! For several IST program relief requests, the staff identified certain action items for the licensee
! to complete. These action items are identified in Section 6.0 of the TER and should be addressed within one year from the date of this SE or by the end of the next refueling outage, whichever is later, unless otherwise stated, in addition, the licensee should address program scope issues identified in Section 6.0 of the TER within one year from the date of this SE or by the end of the next refueling outage, whichever is later. Licensee actions to address the action items in this SE are subject to NRC inspection. The licensee is requested to respond to NRC within one year of the date of this SE describing actions taken, actions in progress, or actions to be taken, to address each of these items.
-a .
3.0 CONCLUSION
The Perry IST program requests for relief from the Code requirements have been reviewed by the staff with the assistance of its contractor, BNL. The TER provides BNL's evaluation of these relief requests. The staff has reviewed the TER and concurs with the evaluations and recommendations for granting relief or authonzing attematives. A summary of the relief request determinations is presented in Attachment 1. The authonzing of alternatives or granting of relief is based upon the fulfillment of any commitments made by the licensee in its basis for each relief request and the altomatives proposed. The implementation of IST program and relief requests
' is subject to inspection by NRC.
The licensee should refer to Section 6 of the TER for a discussion of action items identified during the review. The licensee should address each action item in accordance with the guidance therein. The acWe items identified in Section 6 of the TER should be addressed within one year of the cate of this SE or by the end of the next refueling outage, whichever is later, unless otherwise specified in the TER.
The staff concludes that the relief raquests as evaluated and modifed by this SE provide reasonable assurance of the operational readiness of the pumps and valves to perform their safety-related functions. The altematives proposed in relief requests PR-2, PR-3, PR-6, VR-6, VR-7, and VR-10 (in part) are authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that they provide an acceptable level of quality and safety. The attematives proposed in relief requests PR-4, PR-5, VR 4, VR-5, and VR-9 are authorized pursuant to 10 CFR 50.55a(a)(3)(ii) on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. Relief is granted to relief requests VR-1 and VR-3 pursuant to 10 CFR 50.55a (f)(6)(i) on the basis that the proposed attematives are authonzed by law and will not endanger life or property or the
- common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Principal Contributor: Joseph Colaccino, DE/EMEB Date: August 9,1999 I
.i n s f o t h h 1 h
o e on it t it n .
i t det f in e5wa 5 ia n w5E h 3
in waad 5r o A
c u ene lcsel e i edc i e 5. S rc edc0n edce 5.foi r nntnr ven0 ven5ia ven0 ),
e p
C i
z a 5 ).
i za i z a 5
_ R oei cc s ede airdR(
i d t norF) i t
ai rdRiM morF)d
)
(
t airdRim morF)i i
(
N f f t l t ede r ehocC( 3 ehu cC(3eo 99 eh cC( e o 3 r
- t aaeo SthmCn e Aaa1 l
t t
u c 0 )a t l
t c(d1 t
0 )a a9 Aaa1t t
t u c 0 )a n t
- ( Aaa1 (i deo46. se f
se l
e o n s e 4 o e l
r a o sge nr i
v n wu f s n C1d me n it h ct o ss i
oMe t
a h t s y
r i rl u a eat a S n g i
wga de t
r n t etcOta oaRdg er T r upo e v t nn vu S edn t oi t d i ndi l h i eaEe md l
ner ,Rcc aaic t
_ E U
l Ahs
- d o
- l uh setgr a aeMr r rS d ocle s eo t e cd drb l
ai p uAa n h nApnr e e iord Q deT x n o ai r E emf s o Cee ,a chcgv gs pe e2 q
z it wfes2tcCuo i ol R o r nin mr h2 se u1 A pr s,0 d s .w r .y p a yd ss idi F r u phu6 eit mnpo e p1 .
_ E or t
a an d de ur al doe er r t ,1 oit I
L P t bt nne , ui 25 r i 6s E tsrk e k t in e hi g5 pt r
iu2 q1 1eu R eoe s e odnua ht n9 r oba 00 0 0. e 0 erl a E Tww Tmaq Wia9 wr1 i Fv<>R>pv
_ V :
_ 1L s h TA p t
NV d nm20 o
- don ED n au0
, P C- E 1
5 ams MN t no Sl g HA C ei t s
p Ci1 l
1 s p nec na P F 2d ini A P oc m u H gE n m n vreps TM i pf i p e1 a u p u TU mtn
,l Se33, r ,
r s sm AP
_ l l o e' l
u eu l
A Ct a00 A Y Cd P 00 oivp R I LWCC utag n
minn
- R RI,C223 it E 1 20 ne P HC EE0 ol n t F RR1 1 C caru O t Y n is R e eys t s
n d n
s A
M m
e r
imla Tn T e o it )
ade t ni v M i ,A c d nat c U u q 2 r 1 y 1 ,A (
2 e ,e S e 6f o 1 ,ds t 5 c 1n 6 e 1i,t v 5 1neio mnr or R ,e c ort s 6es a uaCn
,i e we 6u 6 e 6t su ,o d t r
t q r t r r r tr r ala1 it o al lot are C f ao abe i v6c pao PF PC PVME1A n
Rito
_ 1 2 3 4 Ec Te 2 2 2 2 S
t f s ee . 1 2- 3- 4-i l
eqN uo R R R R Re P P P P R
n h h ,
nh o
t i n it 1 3 i it i
t n waad.5 r o n waE5 h de wa5 -
c i e 5. S cr i
e5 nc t
r A i edm05.
tve z g 5 ),foi e
p edc iv e. a5) n 0 in a a n0 r
C i t ai rdR(M 7 ga5 .
R ai no rF)i r
o dR{im morF)d i
9 . f e o dRi )(
rF)
N r eh cC(3r e t ehocC(3e9 t t i
l cC6 l
t Aaa1 uc 0 )a (i
t n
t t
Aaa1 u c (d10 )a a9 e c 0 )(
Ra1 f
(
f sed e
e r
o nsn ea sn d n ered d
n v o sge eht pi e bus ee io me n t i i ct e sm2c 2 rt r y 5. et r t
u e n l
a a cx oaRdg ereatalA g u 0. e y t a rl a l i
l ve m g nn vuhainm0ubn u h e e la n s edn e v t smt vi l
t oit ner o cl e aaiciRioeqs s,Rccw t t nf r es t st o t an .
l am Ahs t e h wApnr i
eo nMef s odlut at se nhse et eg ua d r _
deT e i iolo r d pi e aerses c mhon t i emf o i
w ts2t v s s o uAf cxvt c u od ucda id p
o se u1 A pr s ,0 cCumt i eeivnie
.wP t r u s s r ed r
i n es mnpo ds .
e p1 dncbneh l
ndt e fo u, _
o r ui oit ri eon uor r is i e et g .
P _' pt a25 i
u2 6sidre o i pl t b latc mra u ng .
r r00 q11 e u leedar ma rluqsf t
i e ab iein t i gl rl sm i
t ob00e0ea e ae i
Fv<>R>pvRbRwir eibos l vf i
Dspc eaa l
nei I t t y -
b-d m t n n e .
2- no a t s _
eit t
s s p y) _
na g Sl a oc pf i
i n m u icto -
i n p l ut mtn n l a7 oe u r
l A dr7 Cd i h y( 1 t s op Hs om Dev Sp mu Rl a _
Cv _
t n ,
d e d )
b e n m n ( eg a e ,
ad e 2. a t a r
)
d t ni v n 1 d n t i
u ( nat c e ,e 1RR 2.
n _
q 2 mnr 6. wt 4 s t ymm a ee e 5 or 4 o n 1e ci R 1neio 1l ,F em ,TnTre e
ort
,iuaCn 6t a su ,o s
6pu r
0 1
e
- 2. uk eu q o sa d mt a43. rte r t t o tr r ala 1.i t r aus r e
C abe v6 c PVME1A i
PPI n P1FSM n -
Rio 5 6 1 Et c 2 2 3 Te S
t f s ee iuo
. 5- 6- 1 l
e qN R R R Re P P V R
)
i e e eg n ht hvi n nh i t h
t h
t o y t l t as de wa5 i i wa i
wa _
i t b toVe n 5 n 5 c
n cn0 e5 edie5 t i nn4d T e5 -
A wi ne .
a ve n0 c edc v
ien0 acm C a e n r esor ia r
ga5 )
. t zr e 5 i
).
i t z a 5 ). i e dR(
R dsspv f i
ai dRi ( aidR( r i
N r rF) mo iF) norF) 3 hnimeg t
iec eus r v o io l
cC( 6 eh cC( rehocC(
t u 3 t
Wl i RPInP e c0)
Ra1 f
(
t l
Aaa1 u c 0 )a (
t l
Aaa1 u c 0 )a (
d .
dey y e gt hy esb l
y l h
i v d e nib ws l
bcm i
b t mee s h r el n t
a m V e u e c nu exs l
eo n bs aem g cnI . ses r
ewS r s t
edn oit xoM b ergdn. cR ef
- u. V sd a ng a r i edg n
l edt e l
sian psi a nr fi o l
_ Ahs -i v iSc Cu r
feT t e euh hi d ,iw de Pd bht uc ceph e ed o
- Mf l sf o s gd aSt bel i He
- o l ad nd nl g t
co l f ngm
- - g l hlo s cin ef
. l wpw i i ts ei sen e nit c^ vson ng _
teme iis s s so g .
_ i s e gi
_ F nrc r
Vfoga ir ri c e einl v
f etiin l
vie aux r Oeuex r t ce ani l dh t l
vnt a oas r t i
Vde SpoTe Vaw Vmtste d e -
i o dd g s n
n e
nio a n crc I
a- e v
3
- 0. io l
o Sle ChA l a _
- ;.t s Do Rc4 s8 v _
- a y As) di0d r n
- - fc rl ya 1
ia l
l )
pl F 6 i
pt a epto ap0 g Rm12 F i
T. nt l
uo i o u8 pt n oe st Bs3 HpuE 1
- i t
r Cd )
r8 r r( Rl 1 5 al i
i(
a s aias ,f l
i :s E t a st .
Ve v e S pe1 o I
Sl a l
cVe uRl a v Celvd Gt D02 Mv NSv Pean Lk va S( -
t _
n _
e
_ g
- m , , , ,
n e
r 1 e s
1 e s 2. es 1 i s
- 2. ic i
u q
2.
4r ic 4 r 3.
4r ic 2.
4 r ic e 1ey 1ey c 1ey x c 1ey
,x n c ,x n n , x c n R 0Ee 0Ee 0Ee 0Ee e 1 eu vq 1
eu 1 eu 1 euvq d t trl vq tr l vq t o aar e aar e aar e aar e rl rl C PVF PVF PVF PVF n
_ Ri o 2 3 4 5 Et Tec 3 3 3 3 S
t f s ee . 2- 3- 4- 5-l l
oqN uo R R R R Re V V V V R
n h ,
h o d . h n t 1 t t i
cC n e99 t o i waE 3 i i t
i wa i
t n 5 h n wa5eR d e
a9 n 5 A
c edci e 5. S cr ed i
e c 5. S N i n
d1 s no1 ,
edc i e5 ven0nia iev n0nie e 'f v e i0 it z- n 5 ).
aka5)M . t z a5)h i
C t df t i
3 i R idRi ( air dR(t i f t aai air dRi (
N m vrF)d io 9 no rF)f3o r o eslua idn mo iF) v 3 e n c C )( t3e9 eh cC(1 t
E i
l ee eh cC(
t t
l Aaa1 uc0a (a9d1 t l
Aaa1 u c(2S 0 )a RthveM e t t
A a i1 u c 0 s, ( )a e i x
c d e
i v e n d e
v e d e-pe e i r
i t
d o pc s r x c a pes.
a ey C f
n An a . e e s g eoM i
g r r no et a
_ l r
e prm )t s
edn wt e aO on iu rt t r
_ l oit .
gf re ot o eo Ahs rdE1 un x n ta n s g deT t e saMid iem t
s (p er t en semf o smSn e
r r Ae e Bu i t u nb e
l vl ae i
- o pe ,p t q m vfu p
o m pidA xp t e ne-aor eon,s, eer s
. r r gn rit d cira ae e t
igc P f onie5, k pe l pcyr r n rt p9 es p9 aOs e ,a es0 i ei r xu Pte a1 LJb Rd4 Ed f
e i t
i l
e 0 n2 -
f r u3 d e 4
.0 l 1 o- n n -
n i
le m ti 1 oka 4
. t no r u0F u1
- ir 1 ic t
ae9B, eit e c0d uC rh 724 na oc r
u aFn a c1 t ec077 pf i s s t v 7 i l
c:s nn F55 eo1 FF i
e n1 0, uk s) - -
mtn eM3 a pi53 t oe r dniz1 aE5 Pa nd p
Cd m1 n:F0 ri dda l
i i cs r e ec i
a ,
y hrteo t
aru:s ,8 1 ni v t
nm2 0 Dt u7 Cse1 3 I
s v87 ee ola0 R p7 Cela05 r Gd CvF Cr(u1 RpvFF
- 4 g 2 d n i n 6
- e nr g
. adt n s f 3 ou ny
. e e Ns ss ,
- 2. is cn 1
- 3. ty e aT i l
egn 1 f ee c Ri t 1tnor e yPi c 4 eu 3.i r e g_ 4ev l 1 ibe snc y
ixmcge v 1xq
. 1 1 x ),
_ 1f ,aa t 7 R 0SVr d(Te den nD 0, Ee r e 1 ,f a n e 7. e u n cei el ausf 1t vt e F .
d r 4. ieP p 3. lvq pp qioe t i _
o a 3. leer p1 ar e pe ec r ee l rl s aae _
C P4Rp A1VF ARFrR PVT
_ n Ri o 6 7 8 9 Et c 3 3 3 3 Te S
t f s l
eeuo . 6- 7- 8- 9-l o qN R R R R Re V V V V R
{lf ,!Ilil1l llJ f
e h et o n r it r o t p
o r a s r a n i
t c f ohVn cl i wa e5 5 f ohci s i
e c n A eiPdc vh ei vhsdetco C
i t wSz ei0 5 ).
i t
a wlVer zgpaai t R
N a scir meRo elv t t h o AF) Ri(
cC( 3 sPinmm mesh el v r
oi di nk o r
t t
Avnaa1 aou c 0 )a (
t l
aCtuesf A v R a pi nri l
l i 4 e
we gn enbr s c gey ,
s g nl o v nI ivi sl es v e eit i r nt w i
e aXts a sivel c u o v
l t
a n
r g g oardn f l voioTt ehawelc apf stste d cyV and aped egm t uf edn nCc c ct dho e s n g r. ecst et a u s Aa e ssdt et t
l oit i t
eigce u m s.
Ahs edn Saeloe t l enat oit deT t e t niE Bvhibf ve uoribgmt e inse ef sif o l
t eadMelast e u l
es e n ae o
p aAmScVe r
yrAa .he n r ctorihl 2 rt l l i
i w eustv gof oem mtensder vanf i
er ei l o o ef oreac su agetrhr a t
r kat e ph rorhoishhi P
t pe f g t oteor cmr cc aiiehys r c
e a eier LCbwPPmt t
weehhi pywwcet c a eh n t
r o f
ch i l
e it di e n Cow n- r 5
- t no Ai rg en oe i r
- eit d pi t u na n t la s oc agsdos se r pf i
Aint r nir min t yuteoti i np oe r oqatped n Cd I t
ge e r r
e cn sgxise ema s.
aea etaec cvk l
l a ae nlviv Avlehoae l
t cvd t
n e ,
m 3. y e
r 2 c n
- 2. e i
u q 4 u e 1q R 0r e
e 1 F d tr t s
o ae C PT n
Rio -
Et c -
Te S
t f s 0 ee . 1 l
l o
uo qN R Re V R