ML19309F985
| ML19309F985 | |
| Person / Time | |
|---|---|
| Issue date: | 06/14/1979 |
| From: | Levine S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML19309F986 | List: |
| References | |
| SECY-79-391, NUDOCS 8005020092 | |
| Download: ML19309F985 (50) | |
Text
__
l
+
80050go 3923.
87.2 June 14, 1979 SECY-79-391 l
COM'MISSIONER ACTION 1
For:
The Comission l
From:
Saul Levine, Director, Office of Nuclear Regulatory Research
/
Thru:
Lee V. Gossick, Executive Director for Operation
Subject:
EXECUTION OF THE 2-D/3-D ARRANGEMENT BETWEEN THE FRG FEDERAL MINISTER FOR RESEARCH AND TECHNOLOGY (BMFT),
THE JAPAN ATOMIC ENERGY RESEARCH INSTITUTE (JAERI)
AND NRC Purcose:
To request Comission approval for execution of the subject trilateral arrangement between the BMFT, JAERI and the USNRC.
Discussion:
Over the past 2 years the Comission has been periodically informed of the status of negotiations conducted by the staff with the BMFT and JAERI to reach mutual agreement on the technical scope, tents and conditions for a trilateral cooperative research study of the three-dimensional thermohydraulic behavior of emergency core coolant (ECC) during the refill and reflood portion of a loss-of-coolant accident (LOCA) in a PWR.
The experimental results to be obtained from the full-scale, realistic tcst configurations of this "3-D" program will provide important data for testing advanced computer codes, by which an assessment of the conservatisms contained in the relevant parts of the ECCS evaluation models of Appendix X can eventually be obtained.
Contact:
A. H. Spano, RES/W. S. Farmer, WRSR 42-74347 42-74272
2 InSECY-77-20.(January 17,1977), the Commission was notified of preliminary discussions between the staff and Japanese and German personnel regarding the possibility of a three-party cooperati'.. research effort on the question of ECC flow distribution during the refill and reflood phase of a PWR LOCA. Taking into account various considerations, including the substantial savings to be gained by eliminating large-scale equipment costs and loss of time, the possibility of a joint program provided NRC with an attractive cost / benefit alternative to an equivalent program fully-sponsored by the U.S.
As outlined in the follow-up paper SECY-77-20A (May 6,1977, the proposed cooperation essentially involves (1))a BMFT responsibility to conduct a series of upper plenum thermohydraulic experiments with test configurations representative of U.S./ Japanese, and German PWR designs; (2) a JAERI responsibility to conduct reflood experiments in both a cylindrical core test configuration and in a slab core (two-dimensional) test geometry with upper core support plates representative of U.S./ Japanese and German designs; and (3) a USNRC responsibility to provide for the loan of advanced instrumentation for the German and Japanese experiments, and to perform the required analytical work for the overall program.
This NRC role involves a continuation of much of the code and instrumentation development work it had planned to do in this area, but eliminates the need for the construction and operation of major new facilities.
The Commission was further informed in SECY-78-409 (July 26,1978) of the status of the negotiations and detailed scope of the program developed to that time, and Commission approval was asked for an FY-1980 budget request ~of $13.1 million for NRC support of the cooperative 3-D program.
In approving the FY-1980 3-D budget request, the Commission advised that a $9 million contingency should be used, giving an estimated total NRC 3-D program cost over the FY 1978-84 period of approximately $59 million.
As noted in SECY-78-409, the BMFT had tentatively agreed to a cost-sharing modification of the upper plenum test facility, by which the vessel and core barrel components would be of full length, thereby enabling NRC to obtain data on ECC bypass behavior.
The U.S.
share of the costs of this modification was subsequently I
fixed at $3.25 million (to be provided in the form of loaned data acquisition equipment and related technical services and software development), rather than the
$1 million initially budgeted for this purpose.
3 In December 1978, an additional funding request of
$3.5 million for FY-1980 and 1981 (SECY-78-594) was approved by the Comission to cover the U.S. share of the costs resulting from an additional modification of the BMFT test facility, involving a changt in the downcomer design from 1800 to 3600, to satisfy the bypass flow test conditions of interest to NRC. As l
agreed with the BMFT, the U.S. share of these costs will be provided in the form of specified loaned flow instrumentation and test operation support.
It has now been detennined through subsequent cost i
estimates prepared by the DOE laboratory instrument suppliers that the cost of this added NRC scope will 1
be approximately $4.5 million instead of $3.5 million as requested in SECY-78-594.
These cost additions for the two NRC requested test facility modifications mentioned above, plus a
$1.25 million increase in the estimated cost of providing the agreed upon flow instrumentation grids for the Japanese and German 3-0 facilities will increase the current 3-0 program cost estimate to $58 million, which is within the Comission approved budget but which leaves only $1 million in contingency.
If subsequent changes increase the total program estimate above $59 million, RES will inform the Commission and recomend an appropriate course of action.
The enclosed draft arrangement and accompanying eight appendices (Enclosure 1) set forth the respective responsibilities of the parties, the forms of cooperation adopted, and the provisions regarding the exchange of infonnation, loan of equipment, patents and exchange of personnel.
The prolonged and intensive negotiations required for this cooperative arrangement reflect in part the large financial comitznents borne by each of the parties, as well as the very considerable, detailed planning that was required to develop an appropriate l
definition of the technical objectives, program scope, and related responsibilities of the parties.
l In addition, there was the need to fbd mutual accomodation on a number of such nontechnical issues such as patents, liability and use of results, against a mixed background of different legal and procedural requirements of the three parties.
1 l
4 While two of the signatory parties (BMFT and NRC are governmental agencies, the third is not, the Japanese having requesten that JAERI, which will be doing the technical work for them, sign the arrange-ment rather than the sponsoring (JAEB).
government agency, the Japan Atomic Energy Bureau The BMFT and NRC accepted this proposal, but, in turn, requested that the AEB exchange side letters with the BMFT and NRC at the time of signing, expressing the mutual understanding that the Japanese Government would provide full support to JAERI in its role as the Japanese signatory party to the arrangement.
In particular, the draft side letters negotiated between the three parties (Enclosure 2) specify that the JAEB agrees with and fully supports JAERI in its being their signatory party and in its fulfilling the contractual obligations regarding research program, information dissemination and patents, which are the three areas where the JAEB has direct authority. The BMFT and the NRC parties have agreed to use the same or essentially the same text for their side letters to the JAEB.
It is also agreed that the side letters be exchanged between the Director General of the JAEB and NRC and BMFT officials signing the arrangement.
The subject draft arrangement does not conta'in any special nonproliferation language sir.ce the scope is very clearly related to a nonsensitive area, i.e.,
out-of-pile studies of the thermohydraulic behavior of steam-water mixtures under LWR LOCA conditions. While the Comission's final resolution of the question of nonproliferation language in NRC international agreements as propounded in SECY-79-95 awaits additional clarifica-tion of the Executive Branch position on the proposed recomendation, the Connissioners' coments on SECY-79-95 did not indicate objection to a category of agreements void of nonproliferation language if their scopes clearly indicate that only nonsensitive infonnation and activities are included. The staff believes that the subject agreement is in this category. As noted below, the draft agreement was reviewed and cleared by the Department of State.
No substantive modifications in the enclosed draft of the arrangement are expected.
If any such changes arise as a result of further discussions with the BMFT and JAERI parties, the Comission will be informed.
l l
These actions involve no new resource requirements above those currently budgeted, as set forth in SECY-78-409 and SECY-78-594.
G e
5 Coordination:
This paper has been concurred in by IP.
ELD has no legal objection.
NRR has reviewed this paper and concurs in its recomendation.
The subject arrangement has been formally coordinated with the Department of Energy in accordance with the DOE-NRC Interagency Agreement of August 1978 and there are no issues to be resolved.
The Department of State has reviewed the draft arrangement and given its clearance (Enclosure 3).
Recommendation:
That the Commission approve the subject trilateral cooperative arrangement and that the Chairvan or a Commissioner be designated to sign the arrangement and side letter.
'Saul Levine, Director Office of Nuclear Regulatory Research
Enclosures:
- 1. Principal Arrangement w/8 Appendices
- 2. Draft Side Ltrs fm NRC/BMFT to JAEB and fm JAEB to NRC/BMFT
- 3. DOS Concurrence NOTE: Commissioner comments should be provided directly to the Office of the Secretary by close of business Thursday. June 28, 1979.
Commission Staff Office comments, if any, should be submitted to the Commissioners NLT June 22, 1979, with an information copy to the Office of the Secretary.
If the paper is of such a nature that it requires additional time for analytical review and comment, the Commissioners and the Secretariat should be apprised of when coments may be expected.
DISTRIBUTION Commissioners Commission Staff Offices Exec Dir for Operations ACRS i
Secretariat
=-,
=-.. =...
k.
e i
=
(
4%..
.t
.e 8
5 r.
N.
. =
s.
'e *.
t.
ef
.t,.,
...<],
.g
~-
s
=
1 e.
a,.
e d
j
,e*
( *..
~, * -
1.*
t e,.
g..
.i
- y-
,. w.*(
e.. r.
-, e s
e d
9.-
u **
3
... Z.
.g.r;-.
- J..
s*..
s ?*,q',;
..=~.w? 3.
a' r-as.c-t
.s
<.u...... a,.%..;. e4 '*.- : t-
- u *.; * *:'..?.*>.
3'. : *."i. >.," 3--..
a*
's'. *) y *:e,: f:.s*':'*.%.Cg.' s
..***g' s.n
.,p 4
a
[y,.. j.
- =
.,,4..
.s. e s
.s
.<,..4..h. r*..* :.
.*4..
v r W""
. 3,#.. e.,.d */
J.
3
- ...=.=.-.., '
.9.
,av.-
4
. e s**.<..
.e s
.. s,. <m,.*,, -
e,.w:=....,,c. 1.,t 5,
. ?
.w.
.\\.n......
- ,o..~
...:.=
,p s*
y -
p.
.,.....v..(, -., -
.., ~,..
- 3..
.... v s. (s,
- v. -
3... *. -
..s.,
ge 4
- e * **r? t.,.. 3...f.;. O,-[..
,,w,. i.'./
.. #.w-.T'<.
.e/
..?...,, e.Q+- 2... ".
+
g.ev..
g
+=. k,,,w. aq,g,.,.,. 4..
.s.,
sa....
m.f*1,F* /...;,..*;-
5..,..-
..7
- h. J. v.;r.3'g *
- s
- - t,.*.,
- 'I s
....'.,,,,.rn.--....,,.,.,,,.
.+
s.
., f., 3 4
- r*
. f.*.j s.g
- q f T af*0 *,4-*-).
.,o../,-. ~ ; *".'. *: - ~
, ^
..,.,p 2..
".. - e.
L..
.: w;, :.vg..M. Q. O.f.l,. gg.*
a
. ;,.".,,,,. v T
. ::~.n. 1.:.-..
/
a**
g=
c.
j.
t s- *
..s*.
.',y g...
w
,L f.
~.f
- -,-. ~...
. e.h'**... 7.. :....
.s.
. c w...
. (. t e. *'.
4
- +
]
...O ? J
...e
.... ENCL SU E 1 O R S
. e ar,.l[.%,.^,
- l
., * 'm*.0j.
e,,...,<
.e.~*.
,..~.a.
m
. ~k.n-~..
-.+
..x,.
..v.,
/*
c".
4 y
..e, t
I ~ Q gn*a$.2$.f.$&. ; :$y$Q.1 4,.... O
.N
. r
.$. 6 ';~".. ' &... "* :*.
- {
\\
s l
'. .s. l., '. -.
- 3
- L s.;. A.e.W.+ e.
s
.+
.w
.c..,ra.,.
...# s s/,
- e a
J
-. a..
O.. ;......
.c
+
e
.a
.e s
1 3-
, R a
s.
. ~,,.. + *.
v.
- -y r
i r
.. ~
s
.. =,
1t
... s......
.i.
1 * \\'
.e
~..
. :. gf m. ~...,,.
e
.9
.'s l
e I
i l
1 o
b k
e.-
_-.,-,.m.,
--...s.,
.,w.
,v.
.m t.-
y.
n.w,,.,4 y-c-pn- -g. m
~~
May 23,1979 Draft ARRANGEME4T ON RESEARCS PARTICIPATION AND TECHNICAL EXCHANGE BETWEEN THE FEDERAL MINISTER FOR RESEARCH AND TECHNOLOGY 0F THE FEDERAL REPUBLIC OF GERMANY (B$FT)
AND THE JAPAH ATOMIC ENERGY RESEARCH INSTITUTE (JAERI)
AND THE UNITED STATES NUCLEAR REGULATORY COMMISSION (USNRC)
IN A COORDINATED ANALYTICAL AND EXPERIMENTAL STUDY OF THE THERM 0 HYDRAULIC BEHAVIOR OF EMERGENCY CORE COOLANT DURING THE REFILL AND REFLOOD PHASE OF A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR The Contracting Parties Considering that:
(a) The Federal Minister for Research and Technology of the Federal Republic of Germany (BMFT), the Japan Atomic Energy Research Institute (JAERI), and the United States Nuclear Regulatory Commissicn (USNRC) have a mutual interest in cooperation in the field of reactor safety research, with the objective of improving and thus ensuring the safety of reactors on an international basis;
-.... ~.
3 ARTICLE 1 - OBJECTIVE The BMFT, the JAERI,.and the USNRC, in accordance with the provisions of this Arrangement and subject to the applicable laws and regulations in force in their respectiv.e countries, will join together in a three-party, coordinated analytical and experimental study of the ECC* behavior during the LOCA refill and reflood phases, this study invciving the BMFT-sponsored 3-D upper plenum experiments, as described in Appendix 1, or as amended; the JAERI 2-D and 3-0 refill and reflood experiments, as. described in Appendix 2, or as amended; and the USNRC-sponsored program of 3-D code development, two-phase flow instrumentation development and axperimental analysis, as described in Appendix 3, or as amended.
ARTICLE 2 - SC0pE OF ARRANGEMENT 2.1 Subject to the availability of funds, each Party agrees to provide the personnel, materials, equipment and services necessary to carry out their respective research programs, as described in Appendices 1, 2 and 3, or as amended.
2.2 The BMFT. in accordance with the program described in Appendix 1, or as amendea, agrees to carry out a series of refill and reflood experiments in the BMFT-funded Upper Plenum Test Facility.
2.3 The JAERI, in accordance with the program described in Appendix 2, or as amended agrees to carry out a series of refill and reflood experiments in the JAERI-funded Cylindrical Core Test Facility and Slab Core Test Facility.
2.4 The USNRC, in accordance with the program described in Appendix 3, or as amended, agrees to carry out the TRAC computer code calculations
~
required for the design analysis, pretest predictions and post-test analyses of the BMFT and JAERI test programs included under this Arrangement, and to make available to the other Parties or their contractors the advanced instrumentation set forth in Appendix 3, or as amended. Such instrumentation will be made available through separate loan agreements executed between the appropriate U.S. Government agency or its designated agent and the Party or its designated agent that receives the instrumentation. A model Equipment Loan Agreement is set forth in Appendix 4; this should be used whenever practicable.
2.5 Each Party, as Permitting Party, agrees to permit och of the other Parties to have on assignment at any time a maximum of th:ee mutually agreed upon technical experts for participation in the research program that the Permitting Party is sponsoring, as described in the relevant Appendix 1, 2 or 3, or as amended.
Such assignments shall be in accord with mutually satisfactory personnel assignment agreements to be entered into between the appropriate persons and organizational entities involved in the assignments. A model Personnel Assignment Agreement is described in Appendix 5; this should be used whenever practicable.
.m m.-.
~..
~~
5 2.11 The designated contractors, subcontractors and other representatives referred to in this Article, receiving industrial property of a proprietary nature (as defined in Article 5), shall be under an agreement of confidentiality with either the designating Party or, as may be required, the organization furnishing such industrial property.
AR'TICLE 3 - ADMINISTRATION OF ARRANGEMENT 3.1 Overall responsibility for the administration of. this Arrangement will reside in a comittee (the Steering Comittee), comprised of one senior representative from each of the Parties.
3.2 The Steering Comittee may delegate certain responsibilities for the overall technical coordination and implementation of the research programs included under this Arrangement to a Tachnical Coordination Comittee (TCC), comprised of one senior technical representative from each of the Parties.
In carrying out these responsibilities, the TCC will be responsible for preparation of a detailed program plan for the overall 2-D/3-D Refill and Reflood Program and submit the program plan, within 10 months after this Arrangement comes into force, to the Steering Committee for its review and approval.
3.3 Within the general scope of this Arrangement, if the TCC makes recomendations to the Steering Comittee for appropriate changes in the scope of the research programs described in Appendices 1, 2, and 3, or as amended, such changes shall only be implemented upon approval of the Steering Comittee.
3.4 Details of the organization and administrative functions of the Steering Comittee and TCC are set forth in Appendix 6.
ARTICLE 4 - PATENTS 4.1 With respect to any invention or discovery made or conceived in the implementation of this Arrangement for JAERI and USNRC participation in the BMFT upper plenum research program described in Appendix 1, or as amended, the BMFT as Recipient Party, and the JAERI and/or the USNRC as Assigning Party; and for BMFT and USNRC participation in the JAERI research programs described in Appendix 2, or as amended, the JAERI as Recipie'it Party, and the BMFT and/or the USNRC as Assigning Party; ar.d for BMFT and JAERI participation in the USNRC program described. in Appendix 3, or as amended, the USNRC as Recipient Party and the BMFT and/or the JAERI as Assigning Party, hereby agree, if not agreed upon otherwise, that-
7 ARTICLE 5 - EXCHANGE OF SCIENTIFIC INFORMATION AND USE OF RESULTS OF PROGRAM,
5.1 All information developed or transmitted under this Arrangement i
except for proprietary information referred to in 5.2, 5.3 and 5.4 will be made available to each Party and to its governmental authorities,
- ontractors, subcontractors and other domestic representatives cooperating with the Party. The Parties may also disseminate such nonproprietary information to the public through their customary channels and in accordance with their normal procedures.
5.2 It is recognized by the Parties that in the process of exchanging information, or in the process of other cooperation, the Parties or their designated contractors, subcontractors and other representatives may provide to each other " industrial property of a proprietary nature."
Such property, including trade secrets, inventions, patent information, and know-how, made available hereunder and which bears a restrictive designation, shall be respected by the receiving Party and shall not be used for commercial purposes or made public without the consent of the transmittino Party. Such property is defined as:
(a) Of a type customarily held in confidence by commercial firms; (b) Not generally known or publicly available from other sources; (c) Not having been made available previously by the transmitting Party or others without an agreement concerning its confidentiality; and (d) Not already in the possession of the receiving Party or its
- ~ = - -
contractors.
5.3 Recognizing that " industrial property of a proprietary nature,"
as defined above, may be necessa or for the conduct of a specific cooperative project or may be included in an exchange of information, such property shall be used only in the furtherance of nuclear safety programs in the receiving country.
Its dissemination will, unless otherwise mutually agreed, be limitec as follows:
(a) to persons within or employed by the receiving Party, and to other concerned governmental agencies of the receiving Party, and (b) to prime or subcontractors of the receiving Party for use only within the country of the receiving Party and within the framework of its contract (s) with the respective Party engaged in work relating to the subject matter of the information so disseminated, and i
e
= -
n am.,.
s
9 ARTICLE 6 - LOSS OR DAMAGE OF EQl
LNT 6.1 The provisions vf this Article rply to:
(1) apparatuses, instrumentation, and otner such equipment, hereinaf ter referred to as " loaned equipment," made r
'lable, directly or indirectly, on
, seinafter referred to as the " Loaning a, loan basis by one Party (hereinaf ter referred to as the " Receiving i
Party") to another Party Party") for use in a test facility funded by the Receiving Party
)
under the provisions of this Arrangement, and (2) apparatuses, j
instrumentation and other such equipment, hereinafter referred to as " facility equipment," considered constituent parts of a test facility funded by a Party.
6.2 With regard to loaned equipment that is lost or damaged, the Loaning Party will bear the financial burden of any such loss or damage. Further, prior to the time that the Receiving Party assumes possession and control over the loaned equipment, following installation and checkout before start of the experimental prqram, the Loaning Party shall, subject to the availdbility of funds, also be responsible for the replacement or repair of loaned equipment that is lost or damaged. After assuming such possession and control, the Receiving Party will take all necessary and proper measures to ensure the good working order of the loaned equipment and to minimize the likelihood of any loss or damage to such equipment.
If, during the course of the experimental program, any of the loaned equipment becomes damaged or inoperative, and if repair or replacement or modification of such loaned equipment is determined by majority vote of the TCC to be desirable, the Loaning Party shall be responsible for the repair, replacement or modification of such equipment, subject to the availability of funds.
6.3 With regard to facility equipment funded by a Party, that Party shall bear the financial burden of any loss or damage to such equipment.
Further, subject to the availability of funds, that Party shall also be responsible for the replacement, repair or modification of all such equipment that is lost or damaged during the course of the experimantal program, if such replacement, repair or modification is determined by majority vote of the TCC to be desirable.
6.4 Additional costs arising as a result of delays in the program occasioned by the loss or damage of facility equipment or loaned equipment shall be borne by the Party suffering such additional costs.
6.5 If the loss or damage is caused by a third Party (as defined in paragraph 9.2.4), paragraph 9.4.3 shall apply.
t
- y o, l
i 11 ARTICLE 9 - LIABILITY 9.1 The Parties agree that, except as otherwise provided for in Article 6, the follcwing provisions shall apply in regard to compensa-tion for damages incurred under this Arrangement.
9.'2 For the purposes of this Article, the following definitions shall u
apply:
9.2.1
" Staff" of a Party means the employees of a Party, its contractors and subcontractors perfonning services under this Arrangement, and employees of these contractors and subcontractors performing services under this Arrangement.
9.2.2 " Equipment" or " Property" of a Party means the equipment or property owned or controlled by that Party, or by the contractor and subcontractors of that Party who perform services in connection with research activities under this Arrangement.
9.2.? " Damages" means harm to property or injury to persons.
9.2.4 " Third Party" means a person or other entity not a Party to this Arrangement.
9.3 With regard to First and Second Party damages:
9.3.1 Each Party shall alone be responsible for damages to its property or staff, regardless of where the damages have been incurred, and shall not bring suit or lodge any other claims against anotner Party for damages to its property or staff, except as otherwise 7',--J noted in paragraphs 9.3.2 and 9.3.3 below.
9.3.2 If the damages suffered by the staff of one of the Parties are due to the gross negligence or intentional misconduct of the staff of another Party, the latter Party shall reimburse the former an agreed sum of money which the fonner would be obliged to pay to the person or persons suffering the damages.
9.3.3 If damages to the property of one Party are due to the gross negligence or intentional misconduct of the staff of the other Party, the latter Party shall compensate the fonner for the damages suffered.
9.4 With regard to Third Party damages:
l
-^
.h.....
13
~
i Parties will also choose the chairman of the tribunal. Should the Parties fail to agree upon the composition of the tribunal or the selection of its chairran, the President of the International Court of Justice shall, at the request of the Parties, exercise those responsibilities. The tribunal shall decide any s'ach dispute by reference to the terms of this Arrangement and any applicable laws a6d regulations, and its decision on all questions of fact shall be final and binding on the parties.
Contractors, subcontractors or
~4"##
consultants to the parties hereto shall be regarded as parties to this Arrangement for the purpose of this paragraph.
10.2. This Arrangement shall enter into force upon signature of the Parties, and shall remain in force for a period of 5 years. The Arrangement may be extended for an additional period of time as mutually agreed upon by the Parties.
10.3 A Party may at its option participate in a continuation of the refill and reflood research programs of the other parties beyond the 5-year period of this Arrangement, or as extended, under mutually acceptable terms and conditions.
10.4 Changes in this Arrangement shall be made by mutual consent of the Parties. Technical changes in any of the research programs included under this Arrangement may be made by the Steering Committee in accordance with the provisions of ARTICLE 3 and Appendix 6.
10.5 In the implementation of this Arrangement there will be no transfer of funds from or to any of the Parties, unless otherwise agreed to by the Parties.
10.6 A Party may withdraw from the present Arrangement after providing
- ~
the other Parties written notice of such withdrawal 3 months prior to its intended date of withdrawal. However, such notice may only be given during the first year hfter this Arrangement has come into force.
10.7 In the event that no notice of withdrawal is given by a Party in accordance with paragraph 10.6, the Parties agree that in the event other countries express interest in participating in the 2-D/3-0 Refill and Reflood Program, the Parties will consider such participation under conditions where the interested participating country would make a direct contribution to the 2-D/3-D Program in proportion to its LWR safety research budget.
i i
1 au
,--m..
l January 11, 1979 DRAFT (Figures 1, 2, 3 added 6/1/79)
APPENDIX 1 Federal Republic of Germany Bundesminister fur Forschung und Technologie OBJECTIVE AND SCOPE OF RESEARCH ON THREE-DIMENSIONAL THERMAL HYDRAULIC BEHAVIOR IN THE UPPER PLENUM AND DOWNCOMER DURING REFILL AND REFLOOD I.
INTRODUCTION The Federal Republic of Germany Bundesminister (Ur Forschung und Technologie (BMFT) will fund the design, construction and operation of an experimental facility, the Upper Plenum Test Facility (UPTF),
to provide information on the three-dimensional thermal-hydraulic behavior of steam and water in the simulated upper plenum and downconer of a reactor during the last part of blowdown, the refill and the reflood phases of a hypothetical loss-of-coolant accident in a pressurized water reactor.
The last part of blowdown would be simulated to establish the initial conditions of the refill phase.
II.
PROGRAM A.
Objective The objective of the BMFT research program is to determine the three-dimensional thermal-hydraulic behavior of the fluid in the
~g
[
\\
\\
~
2 (C 9 O(
pe-C8 Y
e'
'\\..
g < g. -
2
%\\ A9 I
[ I'9
- J (Tg%g$$*$
l-
-h 0$bI;.5
'O w.
i*
CCO O
2.C
... n c
/
\\
m I
1 4.r....
-1
/ '-
tb.,
l.
- $+glhW9.\\
46 % 4 %
v 4
i f
~
n.
-.:e tcu s.g $1: i
//
m-.
9 4
<G' g 1
w,
~
. t 9. t m V-@ps a;
i s
1 c4" M A
.,-l' "W.
\\
i
\\.. '. '. gC ~;LLf % ee.
.f Y
e
.an..s
,8
./
, 4_
D.'
,t s
v v
w.
C
.Qe
.j
'. '. L
.V N. %;e. n :'Ud:9.)*?
v e
e e
- g
_ n./,
w s
. <=W e
- =
3
]
y I
m g
w sm En.
.?
E4 i
A i
D
~
e
- a
- N
=6 1
1 m
g
=
?-*n
\\
l l
1
- U i
7
. I L..
/
M
- 1 is t
I i
i i
..na c 1
\\
l
<.m d
I..
_ _ __. ;,I X d il
- ....__.___w
- y, N e
a i
x p;6. % / _
l.
~ - -
.l
~~~---,,;,. 3
.: j i
N.
~
y o
l l
0 h
l
_f
~
D
..l__.C.
j i
O s
carryover to and backflow from the siaulated hot legs during refill and reflood;
.-p.,
water distribution in the upper plenum for combined injection, cold leg injection only, and other ECCS defined in Section II.B.8; delivery of ECC water to the reactor vessel and the effects of condensation during the last part of blowdown, refill and reflood;
)
l three'-dimensional, two phase flow redistribution inside the upper plenum; flow across the core upper plenum interfaces with local check
~'~
of cross flow between end boxes; local pool height formation rate above the tie plate, including frothing and re-entrainment; i
1 liquid fallback to the core as a function cf local steam flow rate and local liquid temperature; l
l
+ rs
_g.
1.
Reactor Vessel Desian Features (Fig. 2) a.
The vessel ID is to be about 4780 mm.
This value is the sum of core barrel OD (full size) and 250 mm radial c um downcomer gap. The downcomer upper annulus in the region of cold and hot legs will be 210 mm.
b.
The wall thickness is~ to be based on ' pressure rating.
The stored heat energy flow from the walls shall be simulated ar necessary.
c.
The vessel to be simulated shall be of full height of the
' simulated PWR.
d.
The hot and cold leg nozzles ID will be 750 mm.
..e.x5 e.
The cold leg nozzles wiil be simult.ted equivalent to
~
3 intact loops and 1 broken loop.
The orientation is shown in Figure 2.
f.
Materials to be employed are to be selected so that the water chemistry is satisfactory for NRC and FRG instrumentation.
D
+
.D
flow resistance, effect of lower plenum level sloshing, obtain-ing correct temperature in lower plenum at the start of the
~ ~
test.
Simulation of the correct flow resistance And structure w
may not be obtainable.
4.
Core Simulation Special emphasis has to be' given to the de' sign of the steam /
water injection mixing device in order to model all the significant hydraulic phenomena expected to be observed in the Cylindrical Core Test Facility (CCTP) and the Slab Core Test Facility (SCTF).
All parties may propuse concepts.
Originators will perform preliminary tests and analyses of their own concepts.
The system selected by the TCC will be constructed, tested in a
~
steam / water environment and manufactured by the BMFT contractor.
Further development will be performed if necessary.
,,_g The functional requirements.for the core simulator are:
a.
To the degree practicable, provide for the correct flow resistance in the vertical direction during the blowdown and refill phases.
- e-
. 5.
Downcoe;c a.
The downcomer will be full-length.
ng=g b.
The downcomer width will be 250 mm in the lower region; the upper annulus just below the cold legs will be 210 mm.
The elevation of the top of the downcomer (upper annulus) will be determined by the designer. '
c.
Realistic flow restrictions such as neutron shielding pads, reactor vessel surveillance sample tube holders, etc., will be simulated ~to the degree practicable.
6.
Upper Plenum Internals a.
The upper structural will be of the KWU type which suitably simulates the W-type, and will include core barrel vent 3e.
valves for B&W simulatien.
Provisions should be made to
~
simulate CE plant conditions, as noted elsewhere. The effect of the inner barrel in the B&W design will be accounted for by the height of the hot leg nozzle above the upper core support plate.
b.
Distance from the lower edge of the upper core support plate (UCSP) to the bottom of the hot leg nozzle will be about 1025 mm.
-e-
g.
Steam generator hot leg drainage is to be simulated.
"~
8.
ECC Injection
- Capability shall be provided to allow the following ECC injections w
with subcooled water:
intact and broken cold legs; intact and broken hot legs; upper plenum; downcomer; and
~
lower plenum.
I Appropriate nozzle arrangements will be provided for possible downcomer and lower plenum ECCS.
w 9.
Auxiliary Systems Auxiliary systems, including steam, water, and nitrogen needed to simulate PWR performance, e.g., accumulator nitrogen *, will be provided in accordance with Figure 1.
To the degree prac-ticable, representative core / hydraulic performance during
~
reflood will be provided.
" Nitrogen may be simulated by air.
-e
different test facilities.
Instrumentation for the UPTF is to be provided by.both FRG and NRC.
FRG is responsible for all control
'~
systems. The USNRC-supplied special instrumentation is listed in
"**e Appendix III.
The total set of instrumentation to be provided shall be comparable with the objectives, facility design ano test program described herein.
Required and desired measurements for the UPTF include the following:'
Recuired Desired Hot Leg Nozzles
-Mass flow rate
-slip ratio
-Void fraction Broken Col,d Leg Nozzle
-Mass flow rate
-Void fraction Intact Cold Leg Nozzles
-Mass flow rate bpperCoreSupportPlate-Massflowrate
-Deentrainment across the boundary and liquid distri-between the core and bution below the upper plenum.
This tie plate and is to bt measured flow distribution by direct methods below the tie if possible.
plate.
C.
TEST PROGRAM The basic test to be performed is a reasonable simulation of a PWR LOCA from the time the upper plenum reaches 9 bars absolute through the last part of blowdown (to establish the initial conditions of the refill phase), and through the refill phase and the crucial
.~
l
1.1.79 Jan. 80 Jan. 81 Jan.
82 Jan. 83 Jan. 84 I
I I
l' il l
Activity Yeara 12 months Deaign e
30 months H:nufacture +
C
~
Construction 24 monthe Tsot e
7 (incl. shake-down)
Analysis e
p e
+
Fig. 3 : Schodulo 3
O O
6 May 23, 1979 Draft o
APPENDIX 2 Japan Atomic Energy Bureau Japan Atomic Energy Research Institute OBJECTIVE AND SCOPE OF RESEARCH ON TWO-DIMENSIONAL THERMAL-HfDRAULIC BEHAVIOR IN CORE AND SYSTEM DURING REFILL AND REFLOOD I.
INTRODUCTION The Japan Atomic Energy Research Institute will fund the design, construc-tion and operation of two experimental facilities:
Cylindri:al Core Test Facility:
to provide information on core and upper plenum, including steam and water carryover (steam binding) and integral system (steam generator and pump simulated) effects during the refill and reflood phases.
The latter part of blowdown would be simulated to establish the initial conditions for refill.
Slab Core Test Facility:
to provide information on two-dimensional, thermal-hydraulic behavior and core flow within the reactor vessel during the refill and reflood phases of a simulated LOCA for a pressurized water reactor.
The last part of blowdown would be simulated to establish the initial conditions for refill.
II.
CYLINORICAL CORE TEST FACILITY PROGRAM A.
Objective 1.
The Cylindrical Core Test Facility i* an experimental test facility designed to model a full-he';at core section of a l
.. b.
Verification of reflood analysis codes.
c.
Collection of the following information to imorove the thermohydrodynamic model in the analysis codes, i.e., (a) multi-dimensional core thermohydrodynamics including the radial power distribution effect, fall-back effect and spatial oscillatory behavior, (b) flow behavior in the upper plenum and the hot legs, (c) behavior of accumulated water at the bottom of the upper plenum including possible counter-current flow and sputtering effect, (d) hydredynamic behavior of the injected ECC wx.ter and the water passing through the steam generator, (e) multidimensional thermohydrodynamic l
behavior in the hot annule* downcemer, and (f) overall oscillatory behavior i.1 the system.
d.
The reference plant for the simulation is ba:ed en a compromise of plant features such that results frca specific tests will be applicable to FRG, Japanese, and United States vendor designs.
B.
Scope of Supply 1.
ReactorVessel a.
The vessel shall be sized to accommodate the 2000-rod core.
t I
s
3.
Lower Plenum Internals The size and structure of the lower plenum and its internal structures are to be based on a simulated PWR design, compromised as necessary for experimental results.
Desired features of the lower structure to be maintained are volume, flos resistance, and obtaining the correct temperature in the fluid in the lower plenum during the test.
4.
Core a.
The core shall consist of a cylindrical configuration of 32 8 x 8 bundles simulating 15 x 15 array fuel including unheated rods, b.
Flow paths at the upper end of the core shall be geometri-cally similar to the PWR end boxes and upper core support plates.
In the remainder of the core, flow paths and geometry shall reasonably simulate the fuel in single-and two phase flow.
c.
Core bypass flow area is included in the downcomer flow area in core I and may be separated in core II.
d.
Power to the core shall be controlled to vary the power distribution to achieve the experimental requirements.
6
. b.
Distance from the upper core support plate (UCSP) to the bottom of the hot leg nozzle is to be as shown in Figure 2-2.
c.
Distance from UCSP to top plate of upper structurals is to be as shown in Figure 2-2.
d.
Upper plenum volume is to be scaled in accordance with the general rule stated in A.2, above.
7.
Reactor Coolant Loops a.
Cold leg breaks shall be simulated.
b.
Actual loop components, e.g., steam generators and pumps shall be simulated.
c.
Connection to containment, and simulation required of containment is to be determined based on experimental requirements, particulary considering last part blowdown and refill phase effects.
8.
ECC Infection Capability shall be provided to simulate the following ECC systems with sub-cooled and near-saturated water:
l
g.
as is used in the 2000-Rod Slab Core Test Facility and the 3D Test Facility to facilitate experimental and analytical coupling of the test results obtained in different test facilities.
Instrumentation for the Cylindrical Core Test Facility is to be provided by both JAERI and USNRC; the USNRC supplisd special instrumentation is listed in Appendix 3.
The total set of instrumentation to be provided shall be compatible with the objectives, facility design, and test program described herein.
C.
Test Program The main part of the test series to be performed is a direct, centinuous simulation of a PWR LOCA from six bars absolute through the last part of blowdown, refill and crucial portion of reflood.
A real time simulation is preferred unless substantial cost savings or other benefits can be obtained without adversely affecting the experimental data.
Emphasis and temporal priority will be given in j
the test matrix to existing ECC systems The test period shall be as shown in Figure 2-3 for core I and II.
A minimum of 20 tests will be performed with each of the two cores (see Table 2-1) perfonned.
Provisions shall also be made to perform separate effects tests.
These separate effects tests are to be used to understand the perform-ance of particular portions of the integral test, e.g., downcomer penetration, and to test effects of particular interest or utility
. III. SLAB CORE TEST FACILITY PROGRAM A.
Objective 1.
The Slab Core Facility is an experimental facility designed to model a full-scale radial and axial section of a pressurized water reactor, a single bundle in width.
This facility will be used tc study the end-of-blowdown, refill and reflood phases of a hypothetical loss-of-coolant accident.
The overall schematic diagram of the facility is shown in Figure 2-4.
The central part of the facility will be a non-nuclear core of 2000 electrically heated rods arranged in a row of eight simulated fuel assemblies.
This core will be housed in a test vessel, which includes a downcomer, lower plenum and upper plenum.
The slab design will be based on eight 16 x 16 fuel assemblies.
Other components shall be sized based on core area scalina, unless otherwise specified by an expert group.
2.
The facility shall provide the capability to reasonably simulate the flow conditions in a PWR in a LOCA from the time the upper 2
plenum pressure reaches six bars absolute (6 kg/cm absolute) through the last part of blowdown, refill and the crucial portion of reflood.
3.
The purpose of the facility is to study : ore heat transfer, core hydrodynamics and ECCS performance.
In particular, the following phenomena are to be studied:
6
. Entrainment, sz-entrainment, re-entrainment, and distribution of water droplets in the core and upper plenum; Pool formation above the tie plate and upper core support plate including water subcooling and frothing effects.
4.
The reference plant for the simulation is based on a compromise of plant features, such that results from specific tests will be applicable to FRG, Japanese, and United States vendor designs.
Application of the test results to various specific vendor designs may require the use of specific geometric nodings of the TRAC code and the use of USNRC-sponsored separate effects tests to support TRAC modeling of plant unique features such as the configuration of structural elements in the upper plenum.
B.
SCOPE OF SUPPLY 1.
Reactor Vessel a.
Vessel shall be sized to accommodate a slab core of eight assemblies with 16 x 16-rod configuration as described in.
At least two such cores plus appropriate spare assemblies will be built, b.
Wall thickness shall be based on pressure rating.
The stored heat energy flow from the walls shall be simulated as necessary.
I
i-i b.
Core barrel is to be full-length.
l c.
External piping will be used for simulation of core barrel vent valves.
3.
Lower Plenum Internals The size and structure of the lower plenum and its internal structures are to be based on a simulated PWR design, compromised as necessary for experimental results.
Desired features of the lower structure to be maintained are volume, flow resistance, and obtaining the correct temperature in the fluid in the lower plenum during the test.
4.
Core a.
The core shall consist of a slab configuration of eight bundles simulating 16 x 16 splitted-array fuel, in accordance with Attachment 1, including unheated rods.
b.
Flow paths at the upper end of the core shall be geometrically similar to the PWR end boxes including simulation of internals as dummy control rod spiders throttling spiders and upper core support plates.
In the remainder of the flow paths and geometry shall reasonably simulate the fuel in single-and two phase flow.
- d.
The downcomer design should provide ECC flow behavior throughout the test which is reasonably representative of that of a PWR downcomer.
Flexibility, such as provision for a vertical partition in the downcomer, phall be provided to achieve acceptable performance Onder countercurrent steam-water flow conditions.
An in-line downcomer such as l
that shown in Figure 2-5 shall be used unless performance evaluations indicate unacceptable results would be obtained.
6.
Vooer Plenum Internals a.
In the presently planned slab core tests of the 2-D/3-D cooperative program, at least two sets of upper structurals are to be used.
One type is to be of the same type as used in the 3-D upper plenum test facility; the other type is to be representative of the Westinghouse PWR design and of the same type as used in the cyl.norical core test facility.
The design of a third type is to be determined.
The tests with each core and upper internals are to be divided in accordance with Table 2-2.
b.
Distance from the upper core support plate (UCSP) to the bottom of the hot leg nozzle to be approxirately 1050 mm (preliminary).
c.
Distance from UCSP to top plate of upper structurals to be approximately 2200 mm (preliminary).
l j 8.
ECC Injection Capability shall be provided to simulate the following ECC l
systems with sub-cooled and near-saturated water:
Intact and broken cold leg injection Intact and broken hot leg injection Downcomerinjection Upper plenum injection Lower plenum injection The slab core facility ECC system shall be designed to maximize mutual benefit and coupling of the 3-D and 2-0 tests.
9.
Auxiliary Systems Auxiliary systems including steam, water and nitrogen
- a.
needed to simulate PWR performance, e.g., accumulator nitrogen, shall be identified and sized.
b.
A supplemental steam supply shall be provided to fulfill the requirements for proper simulation of conditions for testing ECC systems listed in Section B8.
10.
Containment System The containment design shall permit the containment pressure to be a.
controlled during the test based on experimental requirements.
"N ay be simulated by air.
2
. of instrumentation to be provided shall be compatible with the objectives, facility design, and test program described herein.
C.
TEST PROGRAM The main part of test series to be performed are a direct, continuous simulation of a PWR LOCA from six bars absolute through the last part of blowdown, refill and crucial portion of reflood.
A real time simulation is preferred unless substantial cost savings or other benefits can be obtained without adversely affecting the experimental data.
Emphasis and temporal priority will be given in the test matrix to existing ECC systems.
The test period will be as shown in Figure 2-3 for Cores I and II.
Core III* will follow.
A l
minimum of 20 tests will be performed with each the two cores (see Table 2-1).
If achievable, a larger number will be performed, and, if practicable, within the same time period.
Provisions shall also be made to perform separate effects tests.
These separate effects tests are to be used to understand the per-fermance of particular portions of the integral test, e.g., downcomer penetration, and to test effects of particular interest or utility in coupling the 2-D/3-D test facilities.
These tests will also be used to conduct parametric tests as required.
D.
SCHEDULE The overall schedule shall be as shown in Figure 2-3.
j
" Proposed.
. Table 2-2 Preliminary Slab Core Test Matrix for Integral k ',s Core 11#
111/,2/
)))}/
Upper Structure CCTF Core 11 UPTF Coupling CCTF Coupling Coup'ing Test Blockage $ 10 Combined 15 Cold Leg
)
Lower Plenum) 12 Unblocked 5 Cold Leg 4 Vent Valve 4
Cold Leg 5 Hot Leg 1 AlignmentPlateEI El Total 20 20 16 Note:
1/
Any additional tests available with each core are to be allocated in proportion to the tests already assigned.
2f Steam generator tube break test will be considered at a later date.
3/
Four alignment plate tests to be considered at a later date.
4/
Includes some cold leg injection.
5f Proposed.
l t
l
- k l
\\-
1 u
g O
k 1
Bot 1om of :
l Support Safe
\\
o Upper Ne Plenum Loop Nonle Center o
ke L-Soffom of Core P!cle E;--
Top of Heofed Length Core Downcomer Core Boffle Region oe
,e
,e g
1 e
)
f offom of Heefed Length B
n Top of Core Plate a
Lower Plenum '
b, 2
[
Gdd y
g_
O O
j Fig. 2-2. DIMENSION OF PRESSURE VESSEL O
,,-,.-,..-.7,,.---.
-. -- +-.
y,y,,v.y.--,e,,,c.
STEAM SUPPLY LINE (A
}
9
.__ f.A.h l9 E 1 AIR HOT LEO BACK LINE 99 COMPRESSOR
' ' ~
N 4* - *,
E
^
I' I.J f
(INTACT LEG) 3 91r VENT M VE m
N SIMLA.AT{ON Li ha
' b'j; K
j SP
' t
< r
>< r< ry
^
HOT LEO isaTuna WATER
.] 2 j((
~.
h IwarEn. -**- -
SUPPLY I
l TANM-5 i L
-Tang l M
~
/*--4 e^s
- - - - =, -
p 1:rT"ack ~=r t
" Liuu
' e-
@t i~
/ !
. (T
=
Nr GAS
=T/
L(
(~ _( r-- uppen a,:(
SUPPLY SGTEM
- x
[; O r
Plenum
(
fM f
0 (O
M.
wj (w.
=
U C
'35 k ggd pl8 ucsp
. TA N K k,p,i
[
\\
waTEn J
[
u:
s t
so u r
o
'a""
g 4
4 fL t
~~
UE i
m
..1 % ' " -
'7 E
LOWER
\\ PRESSURE[
[
j E
PLENUM s-g,-
(
o f
g$
h
(,_
E VESSEL g,
_ 4
- ,m p
" " o
,( (tPct
- 1
,, W,uNE
{y,,'MNK*
j
,' 8
- ?
u a u
=
4 3
I NEAoER : ::
2 f
('
j I__
((
(
o
./
I {
((LPCI LINE
(
,h (r
l
~
9
'ATER -
((
LPCI PUMP I
msurscanon
)
systru.
f l* *
' [
- i i
WATER FEED LINE
((
~ ',
I
?
I
~
((
(
DRAIN LINE 4
- ;I l
( ~ ~!
f~~-
g
- - TO BE SHARED WITH CYL'NDRICAL CORE TEST FACILTY FIG. 2-4 SCHEMATIC DIAGRAM OF SLAB CORE TEST FACILTY
. Attachment 1 Fuel-Element Specifications to be Modeled in the JAERI 2-0 Slab Core Facility (preliminary)
The main dimensions and design features are given in the following list and figures:
Rod Bundle Distance between rod bundles (centerline to centerline) 230 mm Rod array 16 x 16 Number of heated rods 234 Number of unheated rods (control rod guide tubes) 22 See attached Fig. " Location of Non-Heated Rods" Distance between rods (centerline to centerline) 14.3 mm 1
l Heated rod outer diameter 10.75 mm Unheated rod outer diameter 13.72 mm Heated length 3660 mm Distance upper end of heated length to lower end of upper tie plate 195.6 mm Distance between upper end of upper end box and lower end of upper core support plate (cold) 40.2 mm (hot, estimated) 20 mm Tie Plate (Upper and Lower)
Thickness 15.1 mm Flow hole diameter 10.5 mm Flow holes upper tie plate:
see attached Fig.
" Upper end box to be modeled" l
i l
i l
e
- t.. g Uc5P F
23o a
I q
RV
~
l
]
'r
........____y i
- u. sa en
(
% ]s i
unn I
i d
I i.
3._._l,.
t i
s w
i, s
11 i
h i!
i e
J 4
i
'4 N
?
T~'
\\
.I u
~
.i 1
m g
6
't 4
a
-l t
u t
w
+
i
,s.
W I
m x
a ' w%
n s%
p 1M2- (
-10 7
}iy p
- l Wo,
._.ga s
g s
.n 3
2
.{
i
[
1:
r 1
l
[p g
Y n
r e.
w
_o l
]
'T T' i
l
_. Th
_ I ee FUEL ASSEMBLY TO BE MODLED IN 2-D EXP l
-I
=
- 33,-
)
i O.875 DIA ttF "m ar-i
.~#g a
ldl 4 O
P (C
i 4
f
=*
p I
C 7
I O^U
.... se tu c
n
%l
-e6 y
b%.J.':
I
_t i
L.551 Ola atF 0
TOP VIEW lT.875 Ola 4EF t
A i
0000 n
i 03 OO
^h' hk' 0000000 i
8.424 SQ gegn w
v v
REF 4.750 ttF
~
~
4 i
l 80TTOM VIDt
-".p],C,_ ~, }, ;]..e 9, e
em e
(
UPPER END BOX TO BE MODELED IN 2-D EXPERDENT (SCTF)
(unit : inch) l l
l 9- - - =,..,- - _ - -
May 23, 1979 s
DRAFT APPENDIX 3 United States Nuclear Regulatory Commission OBJECTIVE AND SCOPE OF RESEARCH ON INSTRUMENT DEVELOPMENT AND SUPPLY AND MULTI-DIMENSIONAL COMPUTER CODE DEVELOPMENT AND CALCULATIONS FOR THE 20/3D PROGRAM j
I.
INTRODUCTION
\\
In support of the JAERI and BMFT experimental refill and reflood test programs described in Appendices 1 and 2, or as amended, the U.S. Nuclear i
Regulatory Commission will:
fund, develop, fabricate, deliver and provide operational support for advanced two phase flow instrumentation to be installed in the JAERI and BMFT facilities, and, as described below in Section II-E, provide support for a data acquisition system (DAS) to be installed in the UPTF, and fund, develop and perform multi-dimensional TRAC computer code cal-culations for design analysis, pretest predictions and post-test analysis required for the test program.
II.
USNRC 20/3D INSTRUMENTATION PROGRAM A.
OBJECTIVE
- The objective of the USNRC 20/3D instrumentation program is the measurement of the two-phase behavior of steam and water at the
" The objective of the instrumentation and analysis in this appendix is related to the effects outlined in Appendix I and II.
% measure the mass flow between the core and upper plenum.
B.
INSTRUMENTATION FEATURES To measure the mass flow and void fraction in the nozzles and loops, and between the core and the upper plenum, of the CCTF, SCTF and UPTF several types of instruments will be provided by the USNRC.
The loops of the CCTF are to be provided with spool pieces.
The spool pieces are short flanged pipe sections which contain a drag disk, turbine meter, three-beam gamma densitometer, pressure cell and temperature measuring device.
The spool pieces will be installed in the cold and hot leg piping of the CCTF to measure fluid density, velocity, mass flux and direction of flow to and from the cold-and hot-leg loops during the end of blowdown, refill and reflood phases.
Spool pieces will also be provided for demonstration by installation and checkout in the BMFT PKL hot-and cold-leg piping.
The second series of CCTF tests may include a downconer to upper plenum core barrel vent valve simulation. Mass flow and void fraction will be measured.
The velocity may be measured by a turbine and the void fraction by a string protse.
Mass flow and void fraction measurements are needed for the hot-and cold-leg nozzles of the SCTF and UPTF, which only have simulated loops.
These measurements are needed to define the direction, velocity and steam-water flow to and from the test vessel.
Because I
of the size of these nozzles, it is generally not practical to use l
4 In order to evaluate the local mass flow rate and follow the flow direction and velocity of both steam and water within the core, the upper core support plate and the upper plenum, it is necessary to make local measurements at specified locations (Table III).
Instrumenta-tion capable of doing this and surviving the temperature and steam-water environment of these tests has not been available.
The USNRC is developing several promising instrument types for making local film, void and velocity measurements.
The most promising of these involves the use of film and impedance probes for measuring film thickness
)
and velocity.
Various configurations such as band to band measure-ments, flag to flag, prong to prong, or string probes can be used to measure the velocity and void fraction in cruicial two phase flow locations inside the core and in the upper plenum of the CCTF, SCTF and UPTF.
Cross correlation of probe signal pairs can also be used to derive local velocities.
These instruments, which are under development by the USNRC, give promise to measuring local liquid film velocity, file thickness, steam velocity and void fraction at the locations above.
l The USNRC will provide film probes for the 20/3D test facilities as i
given in the scope of supply section.
Film and impedance probes l
have shown promise for measuring void fraction and velocity in l
preliminary two phase flow tests at ORNL.
Significant advances will, however, have to be made to achieve the accuracy desired.
The USNRC has committed major laboratory resources on this development
)
I effort to improve probe performance and accuracy.
Near term efforts i
. In order to maximize the information from the Stereo lens, software i
for data reduction and image reconstruction is being developed by j
LASL.
By focusing on droplet trajectories and density, it may be possible to determine upper plenum flow velocities and direction.
Film formation and deentrainment should be visible by focusing on upper plenum internals structures.
Initial experiments using the Stereo lens cameras in the JAERI CCTF and the BMFT PXL test facilities provide for recording the test data on tape which will then be returned to LASL for processing.
On request, software packages will be made available when complete for use with the local data acquisition system at each facility so that processing can take place on site.
However, the software package is currently being written for computers in use at LASL (i.e., a CDC-7600 computer), and the facility will have to have access to such a machine or appropriately adapt the software.
A table listing the suggested measurements to meet the objectives of 20/30 Refill /Reflood Program is attached (Attachment 1).
This table also includes some of the facility provided instrumentation where pertinent to the measurement objectives.
Information on the progress of development of USNRC and facility instrumentation will be exchanged between all the Parties.
C.
USNRC INSTRUMENTATION SUPPLY The USNRC proposes providing the quantity and type of instruments given in the following tables for the JAERI and BMFT facilities l
.g.
JAERI CCTF Core 1 8 - instrumented spool pieces (Deliver 7/17/79) 3 - upper plenum LLDs (Deliver 2/1/79) 4 - downconer DDs (Deliver 7/17/79) 6 - core LLDs (Deliver 8/31/78) 3 - downcomer LLDs (Deliver 7/31/78 - 8/31/78) 3 - lower plenum LLDs (Deliver 7/31/78 - 8/31/78) 1 - Stereo lens system (Deliver 2/79)
The instrumentation to be provided by the USNRC for the SCTF Core I, the CCTF Core II and the UPTF are given below in Tables 1, 2 and 3.
The quantities and approximate delivery dates for reference purposes are listed in the tables.
The LLDs and DDs in Table II under the USNRC recommendation for CCTF Core II are to be provided by instruments removed from CCTF Core I.
Spare sensors and transducers will be provided for refurbishing these instruments if needed.
Film and impedance probe modules are not included in CCTF Core I.
Hence, new film and impedance modules will be designed, fabricated and delivered by USNRC for installation in the CCTF Core II heater bundle and vessel internals.
As in the case of Core I and II of the CCTF, Core I, II and III* of the SCTF will reuse, to the extent possible, the same instrumentation in each i
successive core test series.
" Core III is to be authorized.
. The USNRC will provide assistance in resolving unusual failure or readout problems and assist in interpretation of the signals.
Special tools for the installation will be supplied by the USNRC.
Technical supervision will be provided by USNRC contractors on-site at the facilities during initial installation and checkout of USNRC-provided instrumentation and Data Acquisition Systems (DAS) equipment.
USNRC will provide personnel to assist in the n;aintenance of instrumentation and the USNRC-supplied DAS equipment when necessary, as mutually agreed by project managers, and also will assist in checking the in-i strumentation to assure the validity of the data.
JAERI and the j
BMFT will be responsible for providing service requirements, such as electrical power, cooling water, etc. needed for the operation of the USNRC instruments.
D.
DATA HANDLING SYSTEM It is necessary to clearly define the function of each subsystem for data handling, the interface between them, and the responsible party for each (see Table 4-A for the JAERI test facilities and Table 4-B for the UPTF).
1.
Data-taking system: This includes the sens.;, with associated electronics, up to and including the signal conditioners.
The USNRC has responsibility for this work for USNRC provided instrumentation.
1 j
k e
,. F.
NECESSARY INPUT FROM OTHERS In order to provide the instruments as given in the previous lists and tables, it will be necessary for USNRC to receive, on a timely basis,thenecessaryJAERIandBMFTtestfacibtydetaileddrawings, specifications, and related information required by USNRC contractors to design instruments compatible with the facility where they are to be installed.
Delays or mistakes in providing such information will delay delivery of the instruments.
In order to ensure the timely provision of such instruments, the USNRC will keep the BMFT and JAERI informed of the status of the development and drawings of instruments as often as practical.
G.
OPERATIONAL SUPPORT Additional support for the UPTF project will be provided by the USNRC by sending instrumentation technicians, operation technicians, and data analysis experts for facility startup and test operation.
These services will be specified by mutual agreement of the USNRC and the BMFT.
III. USNRC ANALYTICAL SUPPORT PROGRAM A.
OBJECTIVE TRAC (Transient Reactor Analysis Code) has been developed with the objectives of improving capabilities for analyzing postulated transients in full-scale reactors beyond the existing systems code, RELAP.
The improvements focus on the following areas:
- 1) a modular structure to allow flexibility in code organization and problem set-up and to
. Using integral system data from PXL and CCTF and large-scale separate-effects data from UPTF and SCTF, check-out and validate the multi-dimensional best-estimate code TRAC to form a basis for credible predictions of the behavior of a full size PWR during the last part of blowdown, refill and reflood phases of a postulated loss-of-coolant accident.
j B.
TRAC AND INTEGRATION OF TEST RESULTS WITH FULL-SCALE SIMULATION Of the three test facilities included in this test program, only the JAERI CCTF is a full system test with a helted core and external loops with steam generators.
The JAERI SC7F has a full-radius and full-height heated core, with upper and lower plena, all in slab geometry.
There is no hardware in the SCTF to explicitly mock-up the external loops.
The UPTF is a full-scale 360* sector of a reactor vessel without a heated core, and uses steam-water flow from nozzles located below the upper core plate to simulate core flow.
As in the SCTF, there is no hardware for the ex-vessel system.
Thus, each facility concentrates on specialized aspects of multi-dimensional flow within the vessel.
The three participating countries produce PWRs of differing designs and dimensions.
Thus, the geometry of the test facilities is to be a compromise reflecting the main features of the individual designs.
The CCTF will have vessel internals scaled down from a Westinghouse l
17 -
C.
TRAC COUPLING OF TESTS In addition to integrating the individual test results into full-scale t.WR simulations, TRAC will be used, along with engineering judgment, to couple the individual tests (see Figures 1, 2, 3, and 4).
It is understood that, in Figure 3, there is to be generally one iteration between facilities in order tc confirm the boundary conditions.
This coupling will be of two forms:
a'nalytic coupling between test facilities not being run in parallel and experimental coupling between test facilities being run in parallel.
Figure 4 emphasizes the method for the case where the two facilities (UPTF and SCTF) are run as two separate-effects tests with only analytical coupling.
In this regard, the SCTF plays a pivotal role in the geometric coupling because it will have both a set of Westinghouse / Japanese (W/J) internals and a set of KWU internals.
The CCTF is currently 1
planned to have only W/J internals while the UPTF will only have KWU internals.
The first CCTF test series will be finished before the first SCTF tests start, so the coupling between the W/J geometry tests in these two facilities will require analytic coupling by TPAC.
The KWU geometry tests in the SCTF and UPTF will be run somewhat in parallel in time so that coupling can be obtained experi-mentally, using a combination of TRAC and engineering judgment.
For these latter tests, TRAC will supply initial and boundary conditions for the next test in one facility based on the results of the previous tests in the other facility.
Specifically, for the UPTF, TRAC will supply the conditions of the two phase flows to be fomed by the
L P
19 The current understanding is th.it pre-test upward saturated water injection to form a layer of saturated water above the upper core support plate to simulate the potential plugging phenomena in a heated reactor case could be provided by the core simulator.
The superheated steam injection (approx. 350' C) from the core simulator will also help to simulate potential plugging and other reactor conditions.
TRAC analysis will be provided for tests with cold leg injection, combined cold leg and hot leg injection, as well as alternate ECC injection locations.
Necessary model improvements to TRAC are being made so as to be ready in time to accurately predict the phenomena expected to occur during the diverse tests compromising the 20/3D program.
For those facilities to be built after this Arrangement takes effect, TRAC will be used to assist in design studies.
D.
CODE CALCULATIONS For each experiment, adequate code calculations for the geometry of the test facility will be made:
1.
Pre-test prediction 2.
Post-test prediction (measured initial and boundary conditions) will be made when the initial and boundary conditions are significantly different than those used in the pre-test predictions.
i I
. F.
ANALYSIS:
RELATED RESPONSIBILITIES For each test, the calculation and experiment is to be coordinated as follows:
1.
TRAC pre-test prediction, containing boundary and initial conditions for test, transmitted to facility.
2.
Test performed.
3.
Actual boundary and initial conditions transmitted to LASL for post-test prediction.
4.
Post-test prediction transmitted to facility and Quick-Look Report issued.
5.
Test data transmitted to LASL for post-test analysis.
The responsibility and report preparation and interaction between analysis and experiment is contained in Table 6.
l l
TA8LE 2 INSTRUMENTATION FOR CYLINDRICAL CORE II TO BE PROVIDED BY USNRC*
Phenomena Instrument and Location Quantity (Delivery Date)
I.
Upper Plenum 1.
De-entrainment Film probes 4 (5/81) 2.
Local flow patterns Stereo lens 3 (5/81) 3.
Local fluid a Band-to ground probe 4 (5/81) 4.
Local fluid velocity Turbine meters (3V, 1H) 4 (5/81) 5.
Vent flow Turbine meter 2 (5/81)
String probe 2 (5/81) 6.
Pool formation Fluid distr. grid 8x7 (3/81)
II.
Core - Upper Plenum Interface 1.
Upward flow velocity Turbine meter (UCSP) 8 (5/81) 2.
Fluid level in end box Fluid distr. grid Included in I.6.
III. Core 1.
Chimney effect Impedance probe (a & V) 24 (11/80) 2.
Lower plenum / core vel.
Turbine meter 4 ( 1/81)
Drag disc 4 ( 5/81) 3.
Fallback on walls Film probe walls 4 ( 1/81)
IV.
Hot Leg 1.
S.G. drainage Film probe (a & V) 4 ( 5/81)
V.
Downcomer 1.
Local flow patterns Flow distr. grid 5x10x3 (3/81)
^ (1) Tbc instrumented spool pieces supplied for Core I of the CCTF would be required for use with Core II.
(2) The LLDs and DDs from Core I would be refurbished for use with Core II.
9
li l
i'lI l
l:
on tu '
e RAT 4A N
E C
S g S I
g TT g T Y
g LE gE AS pS T
NE L
O i
ER AD t
N P l
I RO I
l 1C rE R
e' 1
R E
A g
EN Ao I
N G
D S
O N
N E
4#O A
Y E
T I
P I
T F
T AS A T
LV f
TR D E
l t
r i
AE N E
l RA I
DVAs 1
^ P i
A I
ON E
F C
GGI N
R I
O D R
A lI E
F ASe C
T N
T
~
I S
^
E T
F A
O T
S I
A A M R
I 8 S
D E
E M
E 4
P W
T A
E ES J
T A
A S
S T
R L Y S
R Y
A B
O T
S S
U F
E N
S N
O Y
O LS S
P I
AL G
A E S I
G T
T A OA T
N t
4R N
N I
I I
l l
L S
IGG AG 1
WE NI
,I V
l I
I I
D B
U DS AS SN Q
O N
I I
C A
S C
N N
A O
fh A
P A
T S
T E
A gR B
l l
' I i
M 3
q d
E T
S R
R T
Y T
E S
N E
YN S N
O G
E A O 4
a L ILmA I
N CmA M
ER N t
NI tN t
i GT I
I G
I I
C RG l
TI A
Tt S D A
P T
SS N
F SS N
N O
C C
l A
I T
A ll D
M,8 g I N
6 O
f T
C
,.A )
I I
C Wet LL
]7 RES N
B S
A U
U (O t l (
F g
g l
l l
ANALYTIC COUPLING PHY51 CAL PHENOMENA gg OF TEST F ACILITY EMPH ASl 7EO b
3 A.
CMEM R EU CWW, i
TRAC C
ImuDING SYSTEM EFFECTS P
gg7gogg TER 05CipTIONS)
INTEGPg g
SYSTEM
- j SYSTEM SIM 1ATION
' "F B.
STEAM BIPCING IN STEAM GErf.RATORS APC EFFECTS u
s PIPING OR.
I 11 C
SEPARATE TRAC C
P h
I CORE A.
RADI AL SCALING OF FLOW K
L c
SIMLt.ATION p
REGIMES IN CORE 8.
3-0 EFFECTS ON OUENCH FRONT MOTION 4,
IIA f
FEATED CORES SCTF C
3
- A.
SCALING OF DE-ENTRAINMENT ON UPPER PLENUM STRUCTURES O*
ECM 118 TRAC me----
T 2
SIM A Ch C.
ILL OF lower PLENUM EA LOWER PLENUM k
D.
INTERACTIONS SETwEEN _
{
STEAM ANO WATER IN THE LPPER PLENUM LASL HARwELL r
m I
TR C SCALING OF CORE / UPPER itC UPTF SCTF EXPER IMENT ALLY SIMa ATION 6
COUPLED TESTS g
/e g
J O
PHASES OF ANAL.YTIC CHECK-0UT IN THE 2-D/3-D PROGR AM FIGURE 1
l e,
e 29 -
l
[
)
stan?
I f
Pum.svsftu.
l ANat YSib Il
' OCTass L O Se t'amaTE EFFCCT TESTS
- CUBCTif1N 1 :
1 r i
t AE SM T S OF AN%v545 i
at&d T S Os ANat'Sa5
,e ygg
. E NC. Ju0CanLN'
. ENC. WNT i
a ganga TNaN S OC 1 C 8** **a f t 0N CF OCTCassikat:QN OF sourcan' CO*4s f BUNS doi.PC AAv CCPCITIONS l
b i t 1'
l FactLITY A C
FACILITV a TES NO C
. tamLICm TMAN $
M ARv CCPctTOr85 0F f>4 F ACILif y CONF inenEO IN Tr(
C I
QTo(a ExPgesangNT T l
l l
1 9
T vtS OCT.itc0Sc...Te ogy,,te,Sg.
,g
?
h CFFECT TES.T ANgvSis EFFECT TES.T ANAYSIS If i f
\\
S aQ.e.N,..,_ s S 40.
.,7N pe(OICTIONT patosCTICpe 7 "o
o u
', as00CL inspeovta(NT l l es00CL IMP 40vtasENT l
. Sv STs..
ANALYSl3 i
l D*
D "D
3'
,c w c
- 1 A0ptgestNT g
wit 80L.Peamy 0F Tsit SgpaAATE EFFECT TESTS
- r VII q p C80 I
Fle6pst 3
TABLE 5 TRAC CALCULATIONS FOR 2-D/3-0 Fiscal Year 78 79 80 81 82 83 84 Facility CCTF Experiments 9
11 2
18 2
Initial Calcs T
Design Calcs*
T Exp't Calcs W
'T4 8
7 8
T SCTF Experiments 20 2
20 Initial Calcs 4
Design Calcs*
W T
Exp't Calcs 10 F
T F
W UPTF Experiments 15 25 Initial Calcs T
Design Calcs*
W W
W
~
Exp't Calcs W
IF F
Full-Scale PWR's 6
15 25 20 25 40 10 l
Approximate number based on full-scale refill and reflood calculations.
Additional shorter calculations will j
also be performed.
. Legend for Table 6 R - Primary Responsibility A - Assistance 1) approval by analysis 2)
R:
instrument developer in all facilities 3)
New model tests:
decision'by Technical Coordination Committee 4)
Within a specified time period (see Appendix 7) reports will be released to the public following a review by the TCC to ensure correctness of data and calculation results.
5) depending on interest of party unless specified otherwise
l 1I l
- l'I I
I I
I I
I I
l' l
1 1 I
=I IEI l _E I
i E=
I g=
l E
gis s. s, i ii. 2 4 -i
.i.,
,j h
I i
j j
I E, I
i 5I III
=I III m
1 I
i 2
k *a l
4 4
y 1
I I
zi I
I I $5I l
'll
$- !E 3
is l
I I
si i
l ix 11 2 25 3 5 I
w 1
I I
-l=
'l 23 g aa i
i 1
9 a.s e
E, 3
i
=
3 g
e s-a 3
i
'?js 5i!
's s
3
! 13]
{ s I g.
l =! s' 53I B
E 1
i m-
_$}E.
y5 L
e
=
E
~
E t
g u
-p p
p.
p W
g g
. u E
I i
t 9
3 J
g E
3 I l I u.
- n E B
l 3
e s1 l
~
=
1 g5 al ca g.
2.5
- s s
.a-
,1,
j, 3l
] i j -] 3 3i l.
a-
., c.
as m
a l
.i 1
g',
3
{.
j
-] : y
.3 I
e is.,
4
. y1 F
1a j11 1
-=
1 mil 1
6.1 l
I-f R.
as g_
MASMREIENi$ TO MET OBJfCTIVES OF 20/30 RfFitt/Rifl00D PROGRAM (Continued) cenP0utui ruY5 scat seeCESS MEA 5NaEMNT RElWIREg INSTRUMLNT AVAllA8tE
~
' I' ITT
[R PKL CCTF UPTF SCTF (I)
(2)
II I
II 100*
36 0*
I II 1I1 tipper Be-entreisseet File Flow on Structures 52 Film Probe N
4 6
/56) 12 (12)
Local Flow Patterns 31 Steree Lens N
2 fN II 3
3 f51 1 2
(12)
(IIear Hot-Leg) local Field e 53 String Probe N
3 g) 53 Band-to-ground Probe N(25) 2 4(22) 10 (26) 12 (26 g(22 (12)
P y-Densitometer N
4( I (12)
Local Field Velocity 51 Tusine Meter N
Between Structures Horizontal l'
1 6
6 1
(12)
Vertical 3
3 5
6 Air Pitet Tube F
12 18 1
iO Peel Forsetten Lipsid levels Froth Level P
Liqufd Level Detector N
3 3
(12) 5 8
O LLD F
4 I
P aP Gauge 1
4 25 36 12 (d
Fluid Distriktion Velocity 5
h t
)
y y
~
~
PJ Temperature Olstributten P
T/C (Fluid)
F 5
4 60 12 II T/C (Walls)
F 56 24 Supedeat Probe F
a b
b
i l
III d
ri ill l
- i il l-I c=
l l
l 4
g=
4 i
i.
j t '
~s' d 5. $
I g
l--
I d
i Ig 1 -g I
i--i 3
=
g=
i l --i i
l l
L E II EII I
g zfz--l I
i i
ii a
-a b
f:
a==-11 1
I" l
1 I
I I
a
, u.s I
3 3}
s 1
3 3-5 i
-i
)
'l 5{3 511illijla:: l i_j*' i a I
ie' 18 ??
u 1
1 In
. s si!.
ss n
i l iiEE a
i 3
- I g
{n 5!.
i Il Iljj i
~
si IS s
l i
r, ili! !
l i
l E
i
}=I:
I j
\\
E
\\
E
.i W
[
li.
I s
t il 11 1
i
.t
~~
t P
P 99 5
u...
- AJ
=
Notes and Comments Relating to Attachment 1 1)
P = primary measurement; mandatory to measure key phenomena necessary for code validation and coupling of results between facilities.
S = secondary measurement; optional and back-up to primary measurement; useful in adding understanding of primary measurement.
5 1 = High secondary priority, S 2 = Medium secondary priority, S 3 = Low secondary priority.
2)
N = NRC, F = Facility.
3)
Number of rods /T/C ner rod.
4)
Total number of T/C per core; not all may be recorded during test.
5)
Includes six pairs of staggered rods.
6) 12 unheated rods.
7)
Actual placemer.t of instrumentation determined by TRAC noding.
8)
Facility information based on documents dated:
PKL-II:
4/78, Core:
6/77, Loops CCTF-I:
11/77 UPTF (180'):
3/78 SCTF-I:
5/78
- 9) Located near top of core.
- 10) One/ bundle located just b21ow tie plate; the rest movable vertically.
l
- 11) 3 across 4 assemblies and 3 across 8 asseeblies.
- 12) Re-usable for Core II.
- 13) NRC will calculate if one AP string through center of core can detect radial differences from other AP strings near outer core region.
- 14) 19 probes /LLD; 17 in core and 2 just above tie plate.
- 15) 3 wide-range LLD's with probes spaced - 20 cm and 3 narrow range LLD's with probes spaced - 10 cm apart.
l 1
. 38) Inlet flow from hot-leg spool pieces.
- 39) Covers entire height of downconer.
- 40) NRC requests these azimuthal AP measurements in the downcomer at 2 axial levels.
41)
G, = p, V,Across UCSP, m:
mixture
[aP]
pg L
in End Box.
h 42) p* =
[LLD]
h, 1
2g AP
- 43) Vt=
Across Tie-Plate; Ks2 will be determined K32 PL from ORNL Experiments.
- 44) Knowledge of P and TL gives pL' 45)
In UPTF Q, and Q will be injected from below (see under "UPTF Injection Zone")anditwiilbepossibletochecktheORNLcorrelathnforBounce-Back.
- 46) A separate write-up on the five main instruments at the Core / Upper-Plenum Interface:
1.
Turbine meter at UCSP 2.
AP TIE-PLATE TO UPPER PLENUM 3.
LLD in End-Box 4.
AP across Tie-Plate 5.
Conductivity probe below End-Box will show how back-up infonsation on important processes can be obtained.
- 47) For JAERI facilities, the modified string probe will give void fraction (a < 0.90) in up-flow, which will give useful input to UPTF spray simulation.
- 48) When there is negligible liquid in the end-box, for high upflow, the mixture mass flow rate is determined from
- ACROSS TIE-PLATE = K O Y 23 n M Turbine Meter
=Y M = MMEN M g
The assumption used to interpret these measurements is that cross-flow is neglected between End-Boxes so it is possible to relate Tie-Plate AP with UCSP velocity.
Justification of these relations is dis. cussed in a separate write-up.
9
(
Jan. 4, 1979 ORAFT APPENDIX 4 MODEL EQUIPMENT LOAN AGREEMENT THIS AGREEMENT, entered into as of by and between the (Loaning Party) and the (Receiving Party):
MiEREAS, the United States Nuclear Regulatory Connission (USNRC), the Federal Minister for Research and Technology of the Federal Republic of Germany (BMFT), and the Japan Atomic Energy Research Institute (JAERI),
have heretofore entered into a research participation and technical exchange
(
arrangement for "A Coordinated Analytical and Experimental Study of the Thennchydraulic Behavior of Emergency Core Coolant During the Refill a'nd Reflood Phase of the Loss-of-Coolant Accident in a Pressurized Water Reactor" (hereinafter called " Principal Arrangement " which includes the Appendices);
~
WHEREAS, the USNRC is obligated under the Principal Arrangement to make available certain advanced instrumentation and other equipment to the other parties, or their designees, in support of the research effort conducted pursuant to the Principal Arrangement; I
I
~
1.
- C
)
to the furnished for the performance of work under the Principal Arrangement, and to set forth the provisions relating to transportation, use, return, disposition, and care of such instrumentation and equipment.
e ARTICLE 2 - LOANED EQUIPMENT The instrumentation and equipment to be provided under this Agreement, j
hereinafter referred to as " equipment," is described as follows:
(identification of equipment)
~
ARTICLE 3 - TERM Unless otherwise agreed to by the parties, the equipment identified in
,(
Article 2 is loaned to the (Receiving Party) for a period of five (5) years or for such other shorter or longer period as may be necessary to complete the research work for which the eqiupeent is intended.
~n.
ARTICLE 4 - DELIVERY, TITLE, AND RISK 0F LOSS 4.1 The equipment shall be prepared for shipment and shipped by the (Loaning Party), its contractors or designees on or about to the (Receiving Party) at the test facility sita location in the Federal Republic of Germany / Japan designated by the (Receiving Party).
{
t O
i
(
l l
5
.(
4.4*. At the and of the loan period specified in Article 3, hereinbefore, and-except where the equipment is abandoned in place, the (Receiving
. Party) shall bear the costs of preparing the equipment for transport.
The costs of transporting the equipment from the Federal Republic of Germany / Japan shalkbe borne by the United States Government.
4.5 W,le to the equip ent furnished hereunder is and will remain with the United States Government.
4.6 Risk of loss of equipment furnished hereunder and responsibility f
for repair or replacement of the equipment in the event it becomes
(
damaged or otherwise inoperative during the course of the experimental program shall be governed by the applicable provisions of the Principal Arrangement.
4.7 The (Loaning Party) furnishes the equipment hereunder without any warranty, expressed or implied, for any purpose.
ARTICLE 5 - LIABILITY The (Loaning Party) assumes no liability for the safety or performance of the equipment furnished hereunder.
The responsibility in this regard shall be governed by the applicable provisions of the Principal Arrange-t ment and any responsibility of the (Loaning Party) shall be assumed by i(
7-
-(
8.22 If the (Receiving Party) decides to return equipment which the
~
(Loaning Party) hai indicated an intent to abandon, then the (Receiving Party) shall assume the costs of returning such equipment.
m' ARTICLE 9 - PATENTS AND TECHNICAL DATA 9.1 All inventions or discoveries made or conceived in the course of development or fabrication of the equipment furnished under this Agreement shall be governed by the patent provisions of the Principal I.
Arrangement.
9.2 The equipment furnished by the (Loaning Party) to the (Receiving
(
Party) may disclose patented or patentable inventions of others.
The furnishing of such equipment by the (Loaning Party) does not convey a license or rights to use such information or inventions.
i
.A 9.3 Rights in patents and technical data arising out of the use of the equipment exchanged hereunder shall be governed by the provisions of the Principal Arrangement.
ARTICLE 10 - MISCELLANEOUS All rights and responsibilities of the parties to this Agraesent not i
provided for herein shall be determined in accordance with the pro-visions of the Principal Arrangement and in accordance with instructions l
0 m
Jan. 4, 1973
'1 DRAFT APPENDIX 5 MODEL PERSONNEL ASSIGNMENT AGREEMENT This AGREEMENT, entered into as of by and betweenthe(RecipiantOrganizationM)andthe(AssigningOrganizationE):
WHEREAS, the (Signatory Party to Principal Arrangement 3/) and (Signatory Party to Principal ArrangementE)haveenteredintoanarrangemantdated
, entitled, " Arrangement on Research Participation and Technical Exchange Between the Federal Minister for Research an'd Technology of the Federal Republic of Germany (BMFT), the Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear Regulatory
(
Comission (USNRC) in a Coordinated Analytical and Experimental Study of the Thennohydraulic Behavior of Emergency Core Coolant During the Ref111 and Reflood Phase of a Loss-of-Coolant Accident in a Pressurized d-Water Reactor" (hereinafter referred to as the " Principal Arrangement"); and
' WHEREAS, the research participation portion of the Principal Arrangement is being conducted in part by utilizing the (Research FacilityM);and WHEREAS, the affected Parties to the principal Arrangement desire that individuals designated by the (One Signatory Party to Principal M) be assigned to work with the (Recipient OrganizationM)
Arrangement personnel at the (Research FacilityM)intheconductofresearch programs related to the aforementioned Principal Arrangement; and
.~
i l
3
(
ARTICLE 3 - SUPERVISION AND CONTROL 0F THE PARTICIPANT 3.1 The nature, extent and period of each Participant's assignment shall be as mutually agreed by the Parties.
Recall of the Participant y
may be. requested when deemed necessary or desireble.
A
\\
3.2 The Participant will continue to be the employee of the (Assigning Organization /). The(RecipientOrganization1/)willexerciseadminis-f 2
trative control and technical supervision of the Participant's occupational f
activities during his assignment.
It is understood that the Participant shall, as a member of a working team, contribute technically to the However, it is " nderstood that he should be allowed researchproject.
u sufficient time to keep himself informed on the total contribution of g
the (Recipient Organization 1/) to the research program and to advise his employer as to the progress of the program.
--w 3.3 The Participant will be required to observe all rules, regulations, andrequirmentsofthe(RecipientOrganization1/), including,butnot limited to, safety, health, hours of work and conduct.
Leave, time off, and vacations of the Participant shall be in accordance with the policy of the Farticipant's employer; however, it is expected that such leave, etc., will be integrated with the requirement of the (Recipient Org.i.uationl/).
l t
m u
g,y-.
,,.,.-.c y
5
-(
v(4) All charges or expenses for proefums for insurance including any premiums for insurance required by applicable law.
ARTICl,E 5 - LIABILITY a.:
The liability of the parties to this agreement and of the' participant shall be in'accordance with the provisions of Article 9 of the Principal Arrangement.
ARTICLE 6 - PATENTS 6.1 Whenever any invention or discovery is made or conceived by the Participant in the implementation'of this Agreement, the Participant shallpromptlyfurnishthe(RecipientOrganization1/)withcomplete g
information thereon.
The (Assigning Organization /) agrees for itself 2
and its employees that the inventor or inventors shall execute all docu-ments and do all things necessary or proper to carry out the terms of
.~ m Article 4 of the Principal Arrangement.
The (Assigning Organization /) and its Participant waive any and 2
l 6.2 all claims against the Recipient Organization for compensation, royalty, or award as regards any such invention or discovery, patent application orpatent,andreleasesthe(RecipientOrganization1/)withrespectto any and all such claims, including any claims under the applicable laws i
of the (Country of the Recipient Organization) and the (Country of the Assigning Organization).
A =*.
7
(
outs,tdeofthe(ResearchFacility$/)anyinformationbearinga restrictive designation without approval of the (Recipient 0rganization).
m 7.4 Any informatioq which is to be delivered to the (Assigning OrganizationE) or to others r to be prepared for publication or public distribution by the Participant shall be submitted to the (Recipient Organization 1/)forreviewandclearancepriortosuchdelivery, publication or distribution, which clearance shall not be capriciously withheld. 7.5 The application or use of any information exchanged or transferred between the parties under this Agreement shall be in accord-ance with the provisions of Article 8 of the Principal Arrangement.
ARTICLE 8 - MODIFICATION OF ARRANGEMENT No agreement or understanding for varying the terms of this Agreement shall be binding on either party unless made in writing and signed or acknowledwed by the culy authorized officers or representatives of the (RecipientOrganization1/)andthe(AssigningOrganizationE).
ARTICLE 9 - PHYSICAL EXAMINATION The employee proposed for assignment hereunder shall undergo, at the direction of the (Recipient OrganizationE) and at the expense of the (Assigning OrganizationE), a physical examination to be anda by a s.
- ?
~
APPENDIX A AGREEMENT NO. S-
,{
i i
l l
AGREEMENT COVERING OBLIGATIONS AND RESPONSIBILITIES OF THE PART g
The undersigned,
, an employee of (hereinafter referred to as the " Participant")
herebyackncwledgesreceiptofnoticethat(AssigningOrganizationE) 1 has entered into a Personnel Assignment Agreement with (Recipient Organization #).
l The Assigning and Recipient Organizations have agreed that the period of Participant's assignment is _
The undersigned Participant, as a condition of his entrance into the aforesaid plants or facilities and/or having facilities and technical data made available to his for the purpose of work in connection with his assignment- ;uder the aforesaid Personnel Assignment Agreement, understands and agrees to the conditions of the Personnel Assignment Agreement which shall be binding on him as far as applicable, in particular:
A.
The Participant shall conform to all security regulations and i
requirements applicable to the research establishment to which 4
i he is assigned.
e?
k
.(
his work under this assignment shall be subsitted to the (RecipientOrganization1#)forreviewandclearancepriorto such delivery, publication or distribution.
F.
The Partigipant shall not transmit or disseminate outside of (RecipientOrganization1#)anyinformationbearingarestrictive designation without approval of the (Recipient Organization 1#).
G.
During the period of the Participant's assignment he will be under the administrative control and technical supervision of the(RecipientOrganizat'on1!).
i
(
}{.
During the period of his assignment, the Participant will observe all rules, regulations and requirements of the (RecipientOrganization1/) including,bi.+.notlimitedto safety, health, hours of work and conduct.
Leave, time off and vacation.n.11 be in accordance with the policy of the Participant's employer; however, it is expected that such leave, etc., t be integrated with the requirements of the (RecipientOrganization1#).
The undersigned Participant further states that he has entered into no I
agreement with any person conf 1 feting with his agreement herein.
.' l.
.)
i
.s.
- (s u
REFERENCED F0GTNOTES 1.
University of California, operator of the Los Alamos Scientific Laboratory (LASL) acting under contract for the U.S. Departmant of Energy (USDOE).
or Gesellschaft for Reaktorsicherheit (GRS), 5000 Koln 1, Glockengasse 2, Postfach 101650 (hereinafter called "GRS"), a designee of the Ministry (for Research and Technology of the Federal Republic o Germany BMFT).
or Japan Atomic Energy Research Institute (JAERI) with headquarters located at 1-1-13 Shinbashi, Minato-Ku, Tokyo, Japan.
2.
University of California, operator of the Los Alamos Scientific Laboratory (LASL) acting under contract for the U.S. Department of
(
Energy.
or Gesellschaft fur Reaktnrsicherheit (GRS), a designee of the Ministry for Research and Technology of the Federil Republic of Germany (SMFT).
.~.
or Japan Atomic Energy Research Institute (JAERI).
3.
United States Nucletr Regulatory Commission (USNRC).
or Federal Ministry for Assearch and Technology of the Federal Republic of Germany (BMFT).
-l or Japan Atomic Energy Research Institute (JAERI).
.a.
l
~~
May ?3, 1979 DRAFT APPENDIX 6 ADMINISTRATION AND TECHNICAL COORDINATION OF THE ARRANGEMENT The Administration and technical coordination of the Arrangement will be carried out at three levels of responsibility by (1) the Steering Committee, j
(2) the Technical Coordination Committee, and (3) the Committee of Project Leaders (Figure),
i 1.
Steerino Committee A Steering Committee composed of one member designated by each of the Parties and established upon execution of the Arrangement:
(i) shall assume overall responsibility for implementation of the Arrangement; (ii) may delegate responsibility for the technical coordination of the research program of the Parties to a Technical Coordination Committee (TCC) to which each member of the Steering Committee shall appoint one member and an alternate in the event the TCC member is unable to attend a meeting of the TCC.
(iii) shall review the progress of the project and approve the programs of research proposed by the TCC;
t
,0
.- (iv) approve the measurement requirements and analysis methods; (v) conduct review group meetings; and (vi) in regard to the publication of results, take such decisions as may be required to be taken jointly in accordance with Appendix 7, ADMINISTRATION OF INFORMATION AND RESULTS OF RESEARCH PROGRAMS.
1 i
3.
Committee of Project Leaders The Committee of Project Leaders, composed of one member appointed by each of the Steering Committee members, shall be responsible for the detailed management and coordination of the projects required to fulfill the scope and schedule objectives.
Its functions include:
(i) the detailed implementation of TCC decisions; (ii) the detailed planning, scheduling and coordination of tests and analyses in accordance with Appendix 8, TECHNICAL COORDINATION OF EXPERIMENTAL AND ANALYTICAL RESULTS; (iii) the organization of uniform procedures for information dissemination, reporting and documentation; and
g i
{ STEERING COMITTEE TECHNICAL ~00RDINATION C0fMITTEE BMFT Rev:= Em::,. l JAERI Review Group USNRC Review Group Committee of Project Leaders BMFT JAERI USNRC Project Leader Project Leader i
GRS MPR Project Leader NUS Battelle l
l GM KWU ARGE IHI ORNL INEL LASL
g January 15, 1979 DRAFT APPENDIX 7 ADMINISTRATION OF INFORMATION AND RESULTS OF RESEARCH 1.
Introduction This Appendix covers the exchange of information between the Parties e
to enable each Party and its contractors to benefit from the results of another Party.
2.
Principles (a) All experimental data and analytical results are available to each Party and can be used by them in accordance with the provisions of Article 5 of the Principal Arrangement and this Appendix.
(b) A final analysis report for a test series, with comparisons between experimental data and calculations, will be issued jointly by the three Parties and be publicly available.
3.
Procedures e
(a) All experimental data and analytical work shall be delivered to the other Parties as soon as possible. The flow of informa-tion will be in accordance with the Technical Reporting System given below.
(b)
Each Party may publish its own experimental data and the results of its own analytical work.
(c)
Each Party may publish the results of its additional further analyses based on the experimental data or analytical work performed by another Party and made publicly available.
- However, any quotation of unpublished experimental data or analytical work may not be made without authorization by the TCC member of the Party originating the unpublished data or analytical work.
[
T
- -...-=
I May 23, 1979 TECHNICAL REPORTING SYSTEM Step Responsibility Copments Protest LASL Results sent to Facility and Parties prior to test. The Parties Pr: diction may make results available to publin.
Experiment Test Facility a.
Data (proprietary) on initial test conditions sent to LASL for Test performance of post-test calculatien.
b.
Raw data printout (proprietary) sent only to the Parties, within 1 month af ter test.
P:st-Test LASL If initial conditions and boundary conditions are significantly changed, Prediction then a post-test prediction would also be made.
Results would be sent to Test Facility and Parties within 1 month after receipt of information on initial test conditions. The Parties may make results available to public.
Quick Look Test Facility Within 3 months af ter a test, a QLR, comparing the experimental test Report (QLR) data with the results of the pre-test prediction and post-test prediction if necessary, will be sent to the Parties, who may subsequently make the QLR available to the public.
Experimental Test facility Within 6 months af ter completion of a test, an EDR, containing the Data Report experimental data required for the analysis and interpretation of the (EDR) results of the test, shall be prepared and issued to the Parties for their use. The EDR may be released for public dissemination af ter a period of 1 year following completion of the test, or before that time if either the EDR is issued without restriction or if the party issuing the EDR so authorizes its release.
Final Analysis 3 Parties An FAR covering a test series will be prepared under the joint Report (FAR) responsibility of the Parties and issued for public dissemination approximately 1 year af ter completion of the test series.
Jan. 4, 1979 DRAFT l
(
APPENDIX 8 TECHNICAL C0 ORDINATION 0F EXPERIMENTAL AND ANALYTICAL RESULTS
~
Both the experimental investigations of the cylindrical and the slab core test facilities (JAERI) and upper plenum test facility (BMFT) and the analysis development and verification activities are systematically related.
The experimental results are used to verify a code.
In addition to the coupling of the 2D-and 30-tests by code, a coupling i
by engineering judgment is necessary; i.e. some tests have to be performed as " coupled tests." The coupling and interaction of the tests should be done on the basis of the attached flowchart.
A code (TRAC etc.) will be used initially to pe'rform a PWR-system analysis.
With the same code a much more detailed prediction and analysis of the multidiassional facilit4s will be done. With results of both runs and with engineering judgment, the boundary conditions for the tests would be determined. With reference to the enclosed flowchart, it is understood that, in general, there is to be one iteration in each cycle between facilities in order to confirm the boundary conditions.
Depending on which test has been performed earlier, the data from one facility will be considered for the specification of the test condition of the other experiment. The differences of the actual results would be assessed, f
the results of one facility directly fed back as necessarf to the other
,m
Flowchcrt for the interconnection of the 2D-sich,the E -LP -
i
)
experiments and the onelysis l
pus. aresom.
I amairese
~
l Se W 1ed esserete offset teete praattetsa r
~
N g
,e-m if 6.e.
h,,ue,.,,,
mt. e, -e.
~
=,.. me.rt
~
=
..~t De*arslaatien ef e
Detecet.euen of 9
toesary sonststune j
ewse. f ems:11yme 4
6 4
bluer 5
^
Possuty a P.e.A.e./.
=.
=
N '.
no
.,s k
.to e dary easfitions of ano fastuty mftress to tas etaar egersaant g
?
i I
g 4
newzed =,.rsi.
re.
to
,,s,s.
offset test effect %eet 6
3 f
aneasala a
(
i i
t ut. predicti e A
M vt.F*ere%
T sum
=
e.
.e e,
e.e.e t
j puut. sysess.
annarste e
9 om p yra-
.n a
f a
.gpe3.r.ta offect toets y
_W c
.:2 m
J
(
=
-s. --
~
g
4
.t e. '
e e
e eg e
. ~....*
~
,.I e.
- d. 4 =.*.,.,,.
.e
., par-@,J - - ", '.
k.,-...;,,,,s,
. e ~
- 5.,
=k 9,'.
,*ra
,c
- h.; ; ;- s
=e..'
e.
.-y
.-.v
~ss;
- w. g:.,c......
g,..
.= -
s
- 9..
.. u..
v.
4
.e
'.,:, s n.a.. g '. _' f,;, '.,..-
5 y
. DS.'...
~ :-
.r.
'. ?.< s.:
,. s e.
,4 *
- 4.c
....... -- a v.
.......s,..
,' ~..
. A *. 's. +
- p.!
,er -
. e e.
.a.*,. g
.w
,f., 16 -
,...- g v
.n
...p. y ~..s. #. 4.
. =......c; s,.
~
ENCLOSURE 2
.A
- g.,
.d. -.a. ' s.
.y--
.;z's,.+.. -
.m 5 4]," ',. %,., e$ s. {.
'4 }",' D *
- .' ;\\
,W
.w.
.*l
- ' " *..y "5
_,T.<:.'.
e
.~ -
_ '. *qq, '~ *,et r **
..p.~r.
' ?
~.
'~
se.._.
,t,a:.
.a. l l. ~.s,..:.:*.-.~.,r
=,.
n P.
- ^ -
e s.
e
'*..ge'
- ae e.*
e
$i.s.
ee4 8
..e g
I.
8 l
l i
9
May 23, 1979 DRAFT SIDE LETTER FROM USNRC AND BMFT TO JAEB
! have the honor to refer to the arrangement between the Japan Atomic Energy Research Institute (JAERI), the Bundesminister fuer Forschung und Technologie of the Federal Republic of Germany (BMFT) and the United States Nuclear Regulatory Comission (USNRC) concerning research participation and technical exchange in a coordinated analytical and experimental study of the three dimensional thermo-hydraulic behavior of emergency core coolant during the refill and reflood phase of a loss-of-coolant accident in a pressurized water reactor, executed on
,1979.
This arrangement represents a mutually beneficial opportunity for the three parties to work fully and effectively together in resolving certain nuclear safety questions of comon interest. On behalf of the USNRC I would like to express my pleasure at this additional instance of international collaboration between our countries.
The arrangement has been signed for the Federal Republic of Gennany and the United States of America, respectively, at the Ministerial level and the Government Agency level, while the signatory party for Japan is JAERI. Therefore, I would be grateful if the Japan Atomic Energy Bureau would inform the USNRC and BMFT parties that it sgrees and fully supports the JAERI in participating as a signatory party 1.o the arrangement and carrying out its obligation concerning the research program, information exchange and patents, as set forth in the arrangement.
DRAFT SIDE LETTER FROM JAEB TO BMFT AND USNRC I have the honor to refer to your letter of
, 1979 and to the Arrangement between the JAERI, the USNRC and the BMFT concerning research participation and technical exchange in a coordinated analytical and experimental study of the three dimensional thennchydraulic behavior of emergency core coolant during the refill and reflood phase of a loss of coolant accident in a pressurized water reactor, executed on
, 1979.
The Atomic Energy Bureau understands the importance of the cooperative pro.iect in connection with the above-mentioned arrangement.
I hereby wish to inform you that the AEB agrees and fully supports the JAERI in participating as a signatory party to the Arrangement and carrying out its obligation concerning the research program, information exchange and patents, as set forth in the Arrangement.
In addition, I would like to inform you that the funds necessary to carry out the above-mentioned research program, within the authorization of the annual fiscal budget by our Diet and Competent Fiscal Authority, will be supplied.
i
e 9
.y.
.w.
... ~.,.:-
~
r
..g
- :.s,..,*,**.,c:..,'
1*
.i'. -
- .' >,,...e.
.=
y m.
s
. r; s..
- f. g,.. ^
,.j,,-..
<~,.r, 4 -
. s, y. *.
,,o.
.sy
..,. =.. i,.,.
.?..*.,;., a 7,.
%... #,.... s
.e a se,,..
., ?.,,.;
,7 3
'aa.
ev ~ s.
....-. *g 7
vc.
. ~ ~.....,
..m :
'.a. :.,.(
.,,. ' '.. ~
- .. e...
g g,
T..
.f,
1,
.s e. < ;. :
,... w. - -
.y....,.
+.
..,..,g..,.,
f.~. ~. : :. m.g.,.,.y.h
..,.. t.
t.e.*
.. r,.
n : '-. -
- ~
.c:?..,.U;' -
. '.. <.. ;.,....-7.; r. v.';. ?.A
- ~:~.:-.:..
.... y 'y. y..:
ev Q
-,~..,(,
.4 w....
,.s. ;...,...M,,. e.p. 3.. f..,...., -
.u. ; p;
.;,pm...p.Q.
2
.;..t.-.
. y,3 y o
.... *' g...,;.-, f.
z.
3 _.r
.r..q.p
.. p.
.... n,..
v 1,m. >,: s..,...
4
..v v.. y.,,..,,.Q,....,.
~
- 4.-
} Q4
- v. wg.e. M,,. 3:
. % QC. :~ 4,...' :.,,..=~J:.m.r.?g,.j n
- r. 4.. y,,...W,."-;:e~':<.-;. ;..
1, s,..
..e s..
u
- a...,
... ~..,.
- M w.\\u.:.
,t' M.
ey :. w m,.,
+.g y.4. -
c, v. -,-
.. :, s *- u%' '.'~ ' '. ** >'".;'f ~~s.. r&. 9?
, ~..; s.... A s %!.Wr -n '%' t %.. i s."Q'?.~.. ;2.;.p.* O.*
- ~?
,:n
,. f. n... *.h hi.~.5
~
~ ' '.
.'.x..,,...,,..
,.;. s...%.
..,.w x..~,..v. m..,..:. m.. e,.
.s... w,
a.
. N,.: A:..-?. -
.n..
.c
..s.u. :e. c d.,:, *.,,.....,.,w;.., ";,. +..
..$. ;L;?%v.,.'
v l.
m. rm. n :.v. :..,m..,
wr m:.
...... h.....,2 h.
- n.~n.
.v.
s.~..
e,,:.m.g\\'"
. e.
.a
- :s*]. F.M..M,h hh t.a.;f.N.. n h;$v-.a:
g c; *. s.....: -
~-
.. n.u p
~
.Yv,~.f.i.-Q, e.
,.. ' W-
%*.P.
. h#' L R. s..
. n.,c s.?.S.,,
.. ~.,. c g. e.
c
.%...y
,...m-;
.s.......
~
.s
.. J
..a,.-.
..y
. : ~ 2. x..,.,
. ; l'. 4c.. a.'- ENCLOSURE 3
.c.+.~
.e
.r:.,
~..,
s j.,
, O{ * '..,..
.,,.,_q.,
- s
. s... g.
..* A e
r;
- t s
.g..
.e.. a
- u,,...
- f......,..
~
..~,,,r;,..,,
r -
,f.* f.
.,,m.
... u.... -..r-v.
-e
.4.-.s w....
W l ;,..
1
+
.j W. : *.VM. s.*
..p&~g,sQ ~..
3
.- Q U* %;! g. n k.,.s:.% f. %; <.' @ W,,....v. m: ;,.A
%v}t.? y.,rgj.<.. '.6., J,. q.%- f.4.k.~.N.. ~.f -
- .. w*.
w..
. s
,, : >.h
- &,L
&...; y ~.
p.-:....
.. 7
- >~
tu.
i
..,.l*w N= 2..--;..
M.
T:.-
e.v s.2y.
.-f W,j.t.ls r?
.),*y.... z. V &. "2"% sw,a..,ck.;.i: ' ' AG.?..m.,.....
,s. :f...s.
s.-
- f a:.y f
- ~
-. f:.
. ~ '. '.. ' '
- k.,. >
..... ;...,r-..n.s :m..s..,.a.. > -.......
1 m.,....
-~.;,>o.
..,..n.-
..y s
....,. a. n,...
>,;....n y...
.--a a.
...-,.4...
.ee.. v,:
s.
.v 4-
. 1 g.
..,., *.:.(. 4, x....
. ~ '.
. s.
...c
,v
.s..--
.,...t,.
s:.
....v..~
- n. r.n,.....:,;..,.
p.r....
..,. e..
- n. = s.. -
s,.
s u.
. w.. c.. :.
...u.
r s
.. s
. r. -
..t.
...,p..
%.,.,.* N.g, M.. -.
.t
. n-
..e
,,.Q.,,g.,.*
,..:..~
g *. r'.
e
.