ML20127J901
| ML20127J901 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/18/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20127J886 | List: |
| References | |
| NUDOCS 8506270176 | |
| Download: ML20127J901 (28) | |
Text
r;
' Docket 50-368 Enclosure Safeguards Safety Evaluation Report - Arkansas Nuclear Generating Station.
Unit 2 On July 1, 1983 Arkansas was chosen by the International Atomic Energy Agency (IAEA), from the U.S. Eligible List, to come under the US/IAEA Safeguards Agreement.
The required Design Information Questionnaire (DIQ) dated August 22, 1983 was submitted by Arkansas to provide a description of their current operations and material control and accounting procedures. The review criterta used for review of the DIQ was the document:
a
" Instructions for Completing IAEA DIQ - Power Reactors," (IAEA Form N-71/Revi-sion I - November 1976 and IAEA Form N-72/Reviion ! - April 1977) USNRC June 1980.
The completed and approved DIQ is necessary for the generation of the Facility Attachment as prepared by the U.S. Negotiating Team and the IAEA Technical Review Group.
The final approved Facility Attachment must be incorporated as a condition of license in order to implement the provisions of the US/IAEA Safeguards Agreement at the Arkansas Nuclear Generating Station.
i hA F
2 IAEA Safeguards
k ARKANSAS NUCLEAR GENERATION STATION. UNIT 2 IAEA SAFEGUARDS LICENSE CONDITIONS 1.
INCORPORATION OF FACILITY ATTACHMENT:
Pursuant to 10 CFR 75.8, NRC License No. NPF-6 is hereby amended to incorporate by reference codes 2. through 7. of Facility Attachment No. 8 dated JUN 01 1543
, to the US/IAEA Safeguards Agreement.
2.
INTERPRETATION OF FACILITY ATTACHMENT:
for purposes of this license amendment, the Facility Attachment shall be interpreted in accordance with the following:
Facility Attachment Code 2.2 The types of modifications with respect to which information is required, under 10 CFR 75.11, to be submitted in advance are those items stated in Code 2.2.
"Any change in the rated thermal output for continuous operations" means:
Any change that exceeds the rated thermal output for continuous operation as described in Paragraph 14 of the Design Information Questionnaire (01Q)datedAugust 22, 1983, or as modifed in accor-dancewith10CFR75.11(c).
i "Any change in the access routes to the reactor area" means:
Any new entrances / exits involving SNM fuel routes or any deletion or modification of existing entrances / exits involving SNM fuel routes ornewopeningsotherthanshowninParagraph10(Attachment 10.7) and Paragraph 56 (Attachment 56.2) of the 01Q dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
"Any change in the design of the reactor fuel" means:
Any change in the design of the reactor fuel that would exceed the maximum quantity in weight and specifications stated in Paragraphs 24(Attachment 24.1),25,26(Attachment 26.1)and27(Attachments 27.1 and 27.2) of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
"Any changs in the type of fuel used, e.g., introduction of' mixed oxide fuel" means:
Any changes involving the use of fresh fissile material ether than U-235.
"Any change in the method of identifying individual fuel assemblies" means:
Identification method other than the use of fuel assembly serial numbers.
1 "Any change of the refueling equipment or methods" means:
Any introduction of new, additional or modified major 1guipment which would cause a significant deviation from the futi handling process and description as specified in Paragraph 13 of the DIQ dated August 22, 1983, or as modifed in accordancewith10CFR75.11(c).
"Any change in connection with the reactor vessel or its cover influencing access to the core" means:
Any change that would facilitate the introduction or removal of fuel in a manner that circumvents or significantly changes current prac-tices.
f 2
" Introduction of new loop heat removal equipment which will be required to increase the nominal rated core thermal power level" means:
t Any introduction / installation of new, modified or additional loop heat removal equipment which would permit increases in the core thermal output from Paragraph 14 of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
" Installation of any fuel assembly dismantling, decladding or dissolution equipment" means:
The introduction (installation) of equipment necessary to extract special nuclear material from the fuel rods.
"Any change in the health and safety regulations affecting the conduct of inspection by the Agency" means:
Any change in the Licensee's health and safety procedures which would preclude Agency access to areas containing special nuclear material and/or any alteration to the procedures described in Paragraph 54 of the DIQ dated August 22, 1983.
"Any change in the methods of storage for irradiated fuel and of the spent fuel storage capacity" means:
Any change in the information in Paragraph 48 of the DIQ dated August 22, 1983, which addresses spent fuel storage plans, method of storage, design capacity of storage and/or spent fuel shipment.
"Any change in other parts of the DIQ to be submitted when the change has been completed" means:
i Any modification in the other parts of the design information pro-vided in the DIQ will be submitted when the first inventory change report (ICR)issubmittedafterthemodification(s)hasbeencom-plated according to 10 CFR 75.11(c)(2).
Facility Attachment Codes 3.1.3 and 5.1.2 Procedures, as referred to in 10 CFR 75.21 includes, among other things, the provisions for item counting and verification set out in Codes 3.1.3 and 5.1.2.
" Item counting and verification" means:
The continuation of the licensee's current physical inventory taking and material control and accounting procedures employed to verify
^
the existence and/or location of SNM fuel assemblies as described' in Attachments 55.6, 55.7 and 55.8 of the DIQ dated August 22, 1983, orasmodifiedinaccordancewith10CFR75.11(c).
Stmilar inventory data for required material control and accounting reports not gene-rated as a result of a physical inventory, may be obtained from the licensee records.
Facility Attachment Code 6.1.1 "The requirement for reporting of Inventory Change Reports (ICR's) (when calculated)" shall mean:
When calculated every six months per the recording requirements specified in Code 5.1.1.
Facility Attacment Code 6.2
" Concise Notes" means those reports that are required to be submitted pursuant to 10 CFR 75.34 and 75.35 on DOE /NRC Form 740M and prepared in accordance with printed instructions for completing the form.
t l
t 4
j Facility Attachment Code 7.
" Inspection" means:
Inspection or inspections as described in 10 CFR 75.42 and as conducted bydulyauthorizedrepresentatives(inspectors)oftheInternational Atomic Energy Agency (IAEA).
Facility Attachment Code 7.3 Code 7.3 shall not be interpreted as requiring a minimum actual inspec-tion effort or any other obligation on,the part of the licensee to assure that any such minimum actual int,pection effort is applied.
"30 man-days per year if one refueling occurt" shall be interpreted to mean:
The anticipated IAEA inspection effort under ordinary circumstances.
Facility Attachment Codes 7.4.2 and 7.4.3
" Verification of the inventory, i.e., by item counting and identifica-tion" means:
The IAEA inspection effort may include the verification of all, or anyportionof,thelicensee'sSNMinventory(fuelassembliesinthe core are subject to verification only during refueling and not,at anyothertime),
i The IAEA's inventory verification procedures may include confirmation of the stated location and serial numbers of fuel assemblies using procedures that are practical and that are within both the IAEA's and the licensee's technical capabilities, i
l r
l 5
Facility Attachment Code 7.10 The specific facility health and safety rules and regulations to be observed bytheAgency's(IAEA) inspectors,asspecifiedinParagraph54ofthedesign information as of August 22, 1983, provided by the USA means:
Agency inspectors who have previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in vie ~w of a special situation that has occurred at the facility since the inspectors' last visit to the facility.
The briefing will be of a short duration, not to exceed 30 minutes, covering topics deemed relevant by the licensee.
Agency inspectors who have not previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special situation that has occurred'at the facility.
The briefing will
~
be of an appropriate duration, not to exceed three hours, and consist of topics deemed relevant by the licensee.
In either case, the licensee should take into account the Agency inspector's prior training, expertise and experience.
In neither case shall the Agency inspector be subject to any form of evaluation or testing by facility representatives or representatives of the U.S.
Government.
For health and safety reasons, Agency inspectors will be escorted by cualified facility personnel at times deemed appropriate by the licensee.
3.
USE OF EQUIPMENT:
The Agency (IAEA) is normally permitted to routinely use portable equip-l ment for their independent material verifications. However, notwith-standing incorporation of Facility Attachment Code 7.5 in this license, the installation of fixed equipment pursuant to said Code 7.5 is not l
required except in accordance with such additional conditions as may subsequently be added to this license.
4.
TE9MINATION:
Pursuant to the provisions of 10 CFR 75.41, the Commission will inform the licensee, in writing, when its installation is no longer subject to Article 39(b) of the principal text of the US/IAEA Safeguards Agreement.
The IAEA Safeguards License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License No. NPF-6 will be terminated as of the date of such notice from the Commission However, since the IAEA may elect to maintain the licensee's installation under Article 2(a) of the Protocol, provisions equivalent to Codes 2. through 6. of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeguards License Conditions to NRC License No. NPF-6 will remain in effect until the Commission notifies the licensee otherwise.
If this option is not selected by the IAEA, the Commission will then notify the licensee that all License Conditions pertaining to the US/IAEA Safeguards Agreement are terminated.
I l
7 Arkansas - IAEA Safeguards I
j-0041W D#0017 Text prepared on:
1985-01-04 Date of entry into forco: g gy g Saforjuards Agrooment Under NPT betwoon the USA and the IAEA Subsidiary Arrangements Facility Attachment No. 8 ARKANCAS NUCLEAR ONE-UNIT 2 (ANO-2),
facility: UXKR
/
f10A: UXKR Total number of pages:
20 Pago No. 1 Codo General Agreement Part Reference Referenco (Articles)
(Codos) 1, 43(a)
Identification of the facility Facility identiftention codc:
UXKO.
1,1 Namo, ownor_nnd operator Namo:
Arkansas Nucloer One-Unit 2 (ANO-2)
Ownor and operator' Arkansas Power and Light Coit;any.
1.2 Geo<1raphic 1ocation Pope County, Arkansas, VCA.
1.3 Postal aodrosi P.O. Don 600 Russolvillo, Arkansas, 72001 Telephone No. (501) 964 3100 1.4 Qo,5 y_j,pjjna The power st4 tion consists of one pressurited
!!9 t w,4 tor reu.t.tur, 201% f*A( t) 'jro s t thormal h
power.
- h e f u t l l l h'l A ri ' i. *' s #4 1 ruir t%. i l y ! ? - 14 rron t,h t
. Number of e wv>l s os d t.tharijud ne rmally on e
refuolling;
' 0 - 7 ',
'W ir.41 woight of fuel !n a n.+ntios-4 ? ti g *,, t.. I.. m. ' s o e.
b
- .e s i muft f ri'sh fyy1 writ It hererit (ll 2)S):
4.1%
- NumLor of f uul ennemtal tet in Lorc, l '/ /
- froth foot star,.-jo c,tpM.it/;
6) ano p i t '.*. f el, N., f" ' 3 l S '",. <
- .1 '
l'li g
.3 nuu d s i..,,. i.. i o e%.
4 J Wh Y $
l
'e Test prepared on:
1905-01-04 Date Cf entry int] f rco: JW D 1 m Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXNR / P904: UXNR Page No. 2 Code General Agreement part Reference Reference (Articles)
(Codes) 1.4 (cont'd)
- Spent fuel storage capacity: 900
- Fuel rods may be enchanged between fuel assemblies at the time of refuelling.
1.5 Mapa and plans See Design Infonnation Questionnaire (DIQ).
2.
3.1 43, 44, Information on the facilty 46(a)
This facility attachment is based on the design infonnation as of 22 August 1903, provided by USA.
2.1 8
tocation of information Identical sots of the information provided ori the facility are kopt 6t the Agency, et tho facility and at the USNRC 6tcadouncters.
2.2 3.1.1 45 Chances in the design information on the facility to be provided in advance 3.1.4 (With reference to the relevant paragrar.hs in the Oosign Inform.ition Questionnalro).
- Any change in the rated thormal nutput for continuous operation.
(14)
- Any change in the. uccess routos to the reactor area, (lO)
- Any ch..rqo in tho,le.t, lyn of the coac tor fuel.
(24, 25, 27)
- Any change in the tvpe of fun! used o.').
~ ***'"
Introdoctton of nised onido fuel.
(.7 2, 21, 18. )
. Any increase in trae maa tNm enennwnu of the fuel.
(21)
. Any chango in the method of telentif y sty individual fuol ansonhilos.
(11) 0
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Test prepared on:
190 H 1-04 Date Cf entry into forc3: Jyg g y Facility Attachment No. 8 ARKANSAS NUCi. EAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MOA:
UXKR Page No. 3 Code General Agreement Part Reference Reference (Articles)
(Codes) 2.2 (cont'd)
- Any chango in the refuelling equipment or methods.
(41)
- Any change in connection with the reactor vessel or its cover influencing access to the core.
(43)
- Introduction of now irradiation cositions inside the reactor vossel.
(44)
- Introduction of m Igop hwat romoval oquipment which
... os required to increase the nominal rated core thormal powoe level.
(52)
- Installation of any fuel decladding or dissolution equipment.
('s t )
- Any chango in the routes of the shipring cask for irradiated fuel within tho facility.
(50)
Any change in the health and safuty 3.2.2 regulations affecting the conduct of inspection by the Aloney.
(54)
- Any chango in the methods of storago of teradiatod fuel and of the spent fuel storage c.apacity.
(48)
Any change in other parts of the dostgn information to be submitted when the t.hange bs. : byon comploted.
1.
94foquards mop,,1tg u 24 Ae.countancy 3,1 111 a4(b)
Stittr_{.4.L.b1),.3ns.n_e.e.r.of1 eo t hc t r J AE.219.lCA10.9 (91( I The At@-2 nuclear (,wility UxkR constitutes one m.stort,e l b,41anc e earca, UXKR.
P O *,j l D t.* ! fi A j dh 0 y Ui.[i.60.16;.}
""NlADp)0
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Ml'iTIAllLA'l MlLA9}0lll!/01.
Tent' prepared ont' 1995-01-04 Dat] cf entry inta fcrea: Jgg g g Facility Attachment No. 8 ARMANSAS NUCLEAR ONE-UNIT 2 (ANo-2)
Facility: UXKR / MBA: UXKR Page No. 4 Code General Agreement Part Reference Reference (Articles)
(Codes) 9 3.1.2 46(b)
Strategic points which are key Measurement 37, 38 Points (KMPs).
(For their specifications see Code 4. )
(a) For determination of nuclear material flow:
6.3 KMP 1 - Receipts, accidental gains and de-exemptions of nuclear materiel.
.KMP 2 - Nuclear loss and production 3.5, 3.7 HMP 3 Shipments of nuclear material, 6.3,.7.1 withdrawals, exemptions and accidental loss's.
e (b) For dotormination of the physical inventory:
KMP A - Fresh fuel storage and inspection area.
KMP 0 - Reactor core.
MMP C - Spont fuel storago racks and spent fuel shipping casks.
KMP O - Other locations of nuclear material at the facility.
s 1.1.1 46(c)
Physical inventory takini (DIT)
Nominal timing:
As soon as possiblo efter the completi<'n of noch refusilling and befr>ro the ro. actor is closed again.
...... ~
In caso of prolonged shutd % n of ono yee.r or lungor, physir:41 inventory tak tra]s shall to prrformed (.nzr>
1.'
m ; r.'.h t.
Fuol other than that containt d in the coro will bo inventorted at least oncu per year.
6 Mg.........s[.6 0.O... '.
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'T;xt, prepared in: !1925-01-04 Dat3 cf entry into fcreo: gg Facility Atdichment No. 8
- ARKANSAS NUCLEAR ONE ' UNIT 2 (ANO-2)
Facility: ~ UXKR'/ MBA:
UXKR
.A Page No. S s
Code-Gcncral Agreement Part Reference Referencel (Articles)
(Code s )
3.2.1 (cont'd)~
Procedures:
Item counting and identification. Preparation of an itemized invrntory list for each inventory KMP.
,s.
20 Containment-and Surveillance 3.2 3.2.1 46(f),
Strategic points for the aoplication of
- containment and surveillance measures
- - Reactor hall.
- The fresh and spent fuel storage areas
~
including access routes.
3.2.2 73(d),(e)
Installed Aacnev instruments and devices s
-(a' Seals to ensure the containment of the
+
~
, reactor vessel.'
(b) Cameras for surveillance of fuel movements into or out.. of.the r.eactor containment includi'ng the fresh ar.d-spent fuel storage areas.
(c) Seals on shipping casks with spent fuel.
(d) Seals on Agency equ.ipt.ent If there is a ne6d to break a seal cr int'arfare with'the operation of safeguards iritruments, th(. Agency shall be inforn.ed in advance by th'e ' f as tes t mohns.
The nfor;:st.;n f
s h'a l l include the (procar;10) date on u.hicn the
?
dperation gill taka' place.
If a seal is removed in the ab;ence of an Agency inspector M.
~ vithout the'aperator being able to inform the
~.
Agency intpdran:(, a special repr.rt wilj pr o pe r.:J,. puc;fie6 1ri Code G.4.;
- J. 3 6.1 -
'll. 35.5 Cpecific crovisions and' criteria for termination of safeguardson nuclear material iic ne.
.n,...
.. ~.
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Text pr; pared en:
1985-01-04 D:ta of entry ints forcs: JUN 0 2 13gg Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility:
UXKR / MBA:
UXKR Page No. 6 Code General Agreement Part Reference Reference (Articles)
(Coces) 3.4 6.2 36, 37 Specific provisions and criteria for exemoting r.uclear material from safeauards None.
3.5 3.7, 7.1 12(a)
Specific provisions and criteria for withdrawal of nuclear material from safoquards None.
s
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d i.* 1 :. r.
1 Ide 4 Ireement Reference (Articles):
%(b), 55, 90.
EE e
ecifications for Key Measurement Points E O.
Et
-- e de 4.1:
KMPs for the flow of nuclear traterial NE 2
i li
=
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t l
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__ l Change l
. _ _ b a t c h _. __,,,,,
l item l l NRC l IAEA l l
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S I
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l ss 1 l Receipt l for fuel assemblies l One l For each fuel _a_ssembly:
l l
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EE I>
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l assem-l (1) Identification number; l
l BQ2f l N
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l For small quantitles of l As l (1) Weight of compound; l
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l Q/SOHl N l
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l l
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1sotopic composition; l
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2 o
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l
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l l
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g 5 l fiain l
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a
jode 4.1: KMPs for the flow of nuclear material (continued)
[
'l l
Description of.a typical l
l Material l Meas.l KMPl Inventory l
Source dala-l Description lbasist
,i,o
-4 l
l__ltem l
.,l NRC l IAEA l l
I
_l Change l
hatch 1
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l l
l
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l t
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KMP 1 above; l
l l
l 5*-
j l Nuclear loss l One fuel assembly.
l assem_ l (3) Estimated burn-up of each fuel l
l BQlG l M l l (burri-up) l l bly l
assembly (in MWD /tu), date of l
l l
l EE E. ~
t l
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. discharge; l
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l l
l
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=
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____.._____l l
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- g l
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l Nuclear Loss l for fuel assembly l One l (1), (2), (3) As above; l
l BQ1G l M.l (9.
l (decay) l l fuel l (4) Nuclear loss of total plutonium l l BQ2G l M l l
l One fuel assembly.
l assem-l (Pu-241 decay) for each fuel l
l l
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assembly when calculated, in-l l
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l BQ2f l N
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Description of a typical l
l Material lHeas.l (HPl Inventory l________________.___
l Source data l Description l basis l
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batch l.. Item l
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Description of a typical l
l Material l Meas.l l
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_.. _ ____ __l item l l NRC l IAEA l l
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-- u A l Fcr fuel assemblies l One l for_each fuel assembly:
l l
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l assem-l (1) Identification number; l
l BQ1f l N l
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i l bly l (2) Weights of total and fissile uranium l l B.Q2f l N l E$
l l
l for untrradiated fuel; l
l BQ4f l N l "I
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l l (3) Weights of total and fissile uranium l l DQ4G l M l s$
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l uranium and total plutonium as l
l l
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l calculated to allow for nuclear loss l
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l (4) Isotopic composition if availabic.
l l
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C l for fuel assemblies l One l (1) Identification number; l
l BQ1G l M l pc l
l fuel l (2) Weights of total and fissile uranium l l BQ2G l M l C
l One fuel assembly.
l assem-l and total plutonium as calculated to l
l l
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l l bly l
allow for nuclear loss and production l l
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l for irradiated fuel; l
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l (3) Burn-up and date of discharge of v
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l l (4) Isotopic composition if available.
l l
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A l for small guantitles of nuclear material l Not l (1) Weight of compound; l
l Q/SOAl N l
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S 7.2 B l (each less than 0.01 et f cctive kilogram)_l applic_l (2) Weights of total and fissile uran)um. l l Q/S0lll N,M l P
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1985-01-04 D ta cf cntry ints forco: JUN 81 1985 Fccility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (AMO-2')
Facility: UXKR / MBA: UXKR Page No. 11 Code General Agreement Part Reference Reference (Articles)
(Codes) 5.
46(d), 49 Records System 5.1 2.1.2 54, 32(f)
Specific provisions for accountina records 5.1.1 54(a),
Inventory changes (for the soecifications of source data see Code 4.1 above), time of recording
- Receipt (KMP 1):
Upon receipt.
- Nuclear loss (uranium born-up) and nuclear production (KMP 2):
When calculated, including upon dischargo.
- Nuclear loss (Pu-241 decay) (KMP 2):
When calculate'd, including upon shipment.
- Shipment (KMP 3):
Upon shipment.
6.2
- Exemption (KMP 3):
Upon the accounting transfer of the nuclear material.
6.3
- De-exemptions (KMP 1):
Upon the accounting transfer of the nuclear material.
3.5
- Accidental loss (KMP 3):
Upon determining the amount of the loss.
- Accidental gain (KMP ):
Upon determining the amour.t of the gain.
3./,
7.1
- Witndrawal (KMP 3);
Upen withdrawal.
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Tcxt' preparcd cn:
1985-01-04 Dato cf cntry ints fcres: J[Jg g y
~
Fsc"ility f;tt:chment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
FacilIity: UXXR / MBA: UXKR Page No. 12 Code General Agreement Part Reference Reference (Articles)
(Codes) 5.1.2 4.2 54(b),
Measurement (item counting and identification) results used for determination of the physical inventory (for the specifications of source data see Code 4.2 above) and time of recording
- For all physical inventory KMPs:
Upon identification and counting of items duri., the physical inventory taking.
- Itemized list of nuclear natorial inventory:
Beforo inventory verification.
5.1.3 54(c)
Adjustments and corrections, time of recording
- Shipper / Receiver difference:
Not relevant.
- MUF:
Normally identical to zero.
- Corrections:
Whenever errors have been found.
5.2 2.1.2 56 Soecific crovisions for operatinq records 5.2.1 56(a)
Operatina data used to establish chanqos in the quantities and composition of nuclear material s
- Location of each fuel assembly at any time.
- The relovant source data with respect to nuclear loss and production, including:
(a) The :.cnthly integrated thermal r., owr produced by the reactor; and (b) The estimated burn-up (in MWD /t) for each fuel assembly.
-- Deato and duration of any reactor shutdnwn.
- Date and description of any dismantling operation of a fuel assembly for pin e x c hang e.
h.
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W ii N w d $2 *a v U Ci u m.di j ppi T;xt prepared En:
1985-01-04 D:t3 cf cntry int] f,grea: JUN 0 2 ggg Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA:
UXKR Page No. 13 Code General Agreement Part Reference Reference (Articles)
(Codes) 5.2.2 56(b)
Calibrations Not required.
5.2.3 56(c)
Sequence of the actions taken in preparina for and in takino the physical inventory
- At physical inventory KMPs:
Datos and description of the actions taken and the results obtained.
An itemized list of nuclear material inventory af ter completion of inventory taking by the operator but before commencement of verification by the Agency.
5.2.4 56(d)
Actions taken in order to ascertain the cause and magnitude of any accidental or unmeasured loss Dates and description of the actions taken and the results obtained.
5.3 50 Location and lanauace of records At the facility and at the utility headquarters in Little Rock (Arkansas):
English.
5.4 51 Rotention period for racords Fivo years.
5.
10 46(d), 57 Rpports systrm 6.1 3.4.1 61(a), 62 Specific provisiens for inventory chance 63 reports (ICRs}
(.I 1 10 Contents The inventcry changes to L+ reported see those types specified in Code 5.1.1 above.
Will be completed as specified in sections 1 through 4 of Code 10, General Part of the Subsidiary. Arrangements.
Q b d O!!).,h b-f
Il Tcxt pr pared on:
1985-01-04 Data cf cntry in a f;rca: 'M 0 J.g Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR /
F.8 A :
UXKR Page No. 14 Code General Agreement Part Reference Reference (Articles)
(Codes) 6.1.1 (cont'd)
Nuclear loss and production for irradiated fuel assemblies will be reported when cz.lcu lated, including as of the date of discharge. The element code of the initial fuel category will be used in reporting.
5.1.2 Timinq or frequency of dispatch Within 30 days after the end of the month in which receipt, discharge, shipment, exemption, de-exemption, withdrawal or accidental loss or
~
gain occurred or was established.
6.2 3.4.1 62 Specific provisions for concise notes 6.2.1 62(a)
Concise notes explaininq the inventerv changes
- May be attached to ICRs (or nailed separately) containing the data on nuclear loss and production, to state the burn-up in MWD /t of initial uranium for each fuel Batch calculated.
- May be attached tio ICRs (or mailed separately) to explain unusual inventory changes (such as accidental loss) or correction. They may also be used to explain any other part of information included in the reports.
6.2.2 62(b)
Concise notes describing the anticipated operational procrammo; subioct and timing of dispatch
- Planned operations involvir.g removal of the Agency reactor vessel coal, e.g. refuelling, fresh fuel receipts, and spent fuel shipments.
To t,c attached to cr.ch P.ilR (:,cc Code 6.1 '.,
below) and to cover the period until the md of the next refuelling.
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n 's $ s $ e se '
MtthUMUU uuitnuutinn.
l T;xt prepared cn:
1985-01-04 Data cf cntry ints farco:
MUN 0 J g Facility Attachment No. 8 ARXANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility:
UXXR / MBA: UXXR Page No. 15 Code General Ag reement Part Reference Reference (Articles)
(Codes) 6.2.2 (cont'd)
- Forecast for the next refuelling, physical inventory taking or spent feel shipment, including information about the shipment casks to be used and the extent to which these are expected to be fillad.
To reach the Agency at least 30 days in advance, subsequent changes thereto as soon as they are known.
6.3 3.4.2 61(b), 65 Specific provisions for material balance reports (MBRs) 6.3.1 10 Contents
- The consolidated inventory changes to be reported are those types specified in Code 5.1.1 above.
- Will be completed as specified in sections 1 through 4 of Code 10, General Part of the Subsidiary Arrangements.
6.1.2 10 Physical inventory listinos (PIls) to be attached to MBRs The batch data included in PILs will be based on the shippor's data on the initial nuclear material content of the fuel for unieradiated fuel assemblics in KMPs A and 8 and for small quantities and on operator's data for irradiated fuel assemblies in MMPs B and C.
Will be completed af. Specified in sections I through 4 of Codo 10, General Part of the Subsidiary Arrangements.
6.3.3 Timinq or frocuoney of dispatch Within 30 days of the physiccol i.ventory taking under Code 3.1.3 above.
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Tcxt prepared on:
1985-01-04 Data cf cntry into f rca:
JUN 0 J gg3 Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 16 Code General Agreement Part Reference Reference (Articles)
(Codes Y 6.4 3.5 66, 89(b)
Special reports 6.4.1 Specification of circumstances requirinq submission of special reoorts (a) Loss limits:
One fuel assembly.
(b) Changes in containment:
- Physical intogrity of a fuel assombly as an ac' counting unit is accidentally broken:
- Any Agency containment and surveillanco devico, referred to in Code 3.2.2 such as a seal or camera, is interfered with or removed in the absence of Agency inspectors, unless the Agency has been informed in advanco as provided for.
1/
6.4.2 3.5 66, 89(b)
Contents, as aperopriate
- Data when the incident or circumstance occurred.
- Description of the actions taken in order to ascortain the cause of the incident or circumstance and the magnitudo of the loss.
- Causo and features of the incident or circumstance.
- Estimated amount of nuclear material which has boon lost.
7.
47 2 ' ' ' ~
Inspections 7.1 70 02 Mpde of routino inspections Intermittent.
1/ In respect of soals on shipping casks, this requircmont applies only while the casks remain in the facility.
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,,Q Tcxt pr; pared on:
1995-01-04 D;ta cf cntry ints fccco:.g 5 IS$$
Facility Attachment No,'8 ARKANSAS NUCLEAR ONC' UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 17 Code General Agreement Part Reference Reference (Articles)
(Codes) i
.. '. 2 78 Applicable formula and procedure for 7
determination of maximum routine inspection effort Article 78(a) of the Agreement.
7.3 76, 79 Indication of the actual routine inspection effort under ordinary circumstances Indication of the actual routino inspection effort, as far as can be foreseen and assuming-3.1 (a) Circumstances at the facility to be as described in the design information provided; i
2.0 (b) The continued validity of the information on the national system of accounting for and control of nuclear material, as set out in the General Part of the Subsidiary Arrangements; (c) That the refuelling period is as stated in para. 37 of the Design Information.
20 man-days per year.
7.4 72, 73 Indication of the scoce of routine inspections under ordinary circumstances
7.4.1 General
Examination of records, verificatten for nelf-consistency end consistoney wi' h reports.
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1995-01-04 Data cf cntry into forco:
JUN g j gg
~'
Fccility Att:chment N'o. 8-ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Faciilty: UXMR / MBA:
UXMR Page No. 18 Code General Agreement Part Reference Reference (Articles)
(Codes) 7.4.2 At inventory KMPs Verification of the inventory, e.g. by item counting, identification and integrity checks and non-destructive measurements.
7.4.3 At flow XMPs Verification of inventory changos, e.g. by itom counting, identificatiun and integrity checks and non-destructive measurements of fresh and irradiated fuel, including the use of seals on containers of irradiated fuel.
7.4.4 At strategic points for containment and surveillance
- Observation of refuelling and spent fuel removal operations:
- Application, examination and removal of Agency seals used in accordanco with Code -
3.2.2, as well as of other seals;
- Servicing and maintenance of the surveillance equipment.
7.5 73(d)
Arrangements for the use by the Aqoney of equipment for indocondent measurements Specific arrangements for the use of Agericy equipment to be made as the need drisos.
7.6 9.4 71(a)
Duplicates and~sdditional satplos for the Aaoney Not relevant.
/.7 85, 86
.Porsons tn whom a request for any operation or for services _at the facilit,y should ha addressed Vice President for Nuclear Operations Tolephone No.
(501) 371 7901
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TCxt prepared on; 1985-01-04 Dato cf cntry inta fcrco:
JUN 01 1985 Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA:
UXKR Page No. 19 Code General Agreement Part Reference Reference (Articles) j (Codes) 78 contacts at the facility General Manager, ANO Telephone No.: (501) 964 3100 7.9 14, 86 Services and charoos 7.9.1 Services provided by the operator with no charge to the Agency
- Health and safety services (protective clothing, dosimeters).
- Office space for the Agency's inspectors.
- Power supply for the Agency's instruments.
- Personnel for handling the fuel assemblies during their measurements.
- Available equipment for handling the fuel assemblies during their measurements.
- Personnel to escort and facilitate audit activities.
7.9.2 Services provided by tho operator with charges to the Agency e
- Means of communication (telephone, telex, cabic):
According to existing rates.
If any specific request by the Agency ft;r services not covered above gives rise to expenses for which reimbursoment i's requested from the Agency, the Agency shall to notified of the estimated expenses before tta service is performed. The Agency will only reimburse such oxpansas if it has confirmed its init 91 request and agreed in writing to the amoun' involved.
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Tcxt' prepared on:
198!K11-04 0;ta cf cntry ints frreo:
JUN o t nos
~
Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Fccil,,ity : UXKR /. NBA: UXKR Page No. 20 Codo General Agreement Part Reference Reference (Articles)
(Codes) 7.9.3 Mode of reimbursement of the expenses charged to the Agency By cheque, after receipt of the invoice by the Agency.
7.10 3.2 44 Specific facility health and safety rules and regulations to be observed by the Agency's inspectors As specified in paragraph 54 of the design information as of 22 August 1983 provided by the USA.
The Agency inspectors will be informed at the facility by. short briefings at h health and safery r)u,1 t the time of entry into the fac of g
hoc to o
rules as might be required in view of a special situation that has occurred at the facility.
For health and safety reasons, inspectors will be escorted by qualified personnol.
8.
4.1.3 30, 88 Agency statements 8.1 88(a)
A summary statement will be made on the result of each inspection within 30 days of its completion, 8.2-00(b)
A statomont on the conclusions the Agency has drawn from its verification activitics in rospoct of the facility will bo made within 60 days after the end of the month in which the Agency bcs vorified the physical inventory.
The statement will include, as appropriate, cunclusions drawn from:
(a) Records examination; (b) Reports to the Agency; (c) Verification of containment and surveillance measures; (d) Verification of inventory changes; (c) Verification of matorial accountancy; (f) Vorification of the quality ar.d funct,ioning of the operator's measurement system; (g) Activitics in respect of MUF, shipper /
receiver differences and/or losses.
-