ML13322A106

Safeguards SER Based on IAEA 830701 Decision to Include Facility Under Us/Iaea Safeguards Agreement

ML13322A106
Person / Time
Site:	San Onofre
Issue date:	06/18/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML13322A105	List: ML13322A104 ML13322A106
References
NUDOCS 8506270160
Download: ML13322A106 (27)

Text

Docket 50-361 Enclosure Safeguards Safety Evaluation Report -

San Onofre Nuclear Generating Station, Unit 2 On July 1, 1983 San Onofre 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 September, 1983 was submitted by San Onofre to provide a description of their current operations and material control and accounting procedures. The review criteria used for review of the DIQ was the document:

"Instructions for Completing IAEA DIQ -

Power Rea ctors," (IAEA Form N-71/Revi sion I - November 1976 and IAEA Form N-72/Revision I -

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 San Onofre Nuclear Generating Station.

1OIAEOSafe506u18 FD -DC 503 IAEA Safeguards

SAN ONOFRE NUCLEAR GENERATION STATION,.UNIT 2 IAEA SAFEGUARDS LICENSE CONDITIONS 1, INCORPORATION OF FACILITY ATTACHMENT:

Pursuant to 10 CFR 75.8, NRC License No. NPF-10 is hereby amended to incorporate by reference Codes 2. through 7. of Facility Attachment No. 9 dated JUN a 1 1985

, 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 (DIQ) dated September, 1983 or as modified in accordance wth 10 CFR 75.11(c).

"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 or new openings other than shown in Paragraph 10 (Attachment 1) and Paragraph 56 (Attachment 23) of.the DIQ dated September, 1983, or as modified in accordance with 10 CFR 75.11(c).

1 San Onofre -

IAEA Safeguards

"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, 25, 26 (Attachment 5) and 27 (Attachment 6) of the DIQ dated September, 1983 or as modified in accordance with 10 CFR 75.11(c).

"Any change in the nominal enrichment of the fuel to more than 4.1 w/o" means:

Any change in the fuel enrichment from that listed in Paragraph 23 of the DIQ dated September, 1983, or as modified in accordance with 10 CFR 75.11(c), that would exceed 4.1 weight percent U-235.

"Any change of the refueling equipment or methods" means:

Any introduction of new,.additional or modified major equipment which would cause a significant deviation from the fuel handling process and descriptions as specified in Paragraph 13 (Attachment 3) or 41 (Attachment 11) of the DIQ dated September, 1983 or as modi fied in accordance with 10 CFR 75.11(c).'K S

"The introduction/installation of equipment for assembling or disassemb ling fuel assemblies (for fuel-pin exchange") means:

The introduction of equipment necessary to facilitate the removal and/or replacement of fuel rods in assemblies.

"Introduction of new loop heat removal equipment which will be required to increase the nominal rated core thermal power level" means:

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 September, 1983 or as modified in accordance with 10 CFR 75.11(c).

2 San Onofre -

IAEA Safeguards

"The installation of any fuel assembly dismantling, decladding or.

dissolution equipment" means:

The introduction of equipment necessary to extract special nuclear material from the fuel rods.

Facility Attachment Code 3.1.3 "In case of prolonged shutdown of a year or longer, physical inventory takings shall be perfomed once every 12 months" means:

That all special nuclear material not in the core wll be inventoried at least once per year. Fuel assmblies in the core are normally subject to verification only at time of refueling. Book values will be used at other times. The reactor head need not be removed expressly to take a physical inventory of the fuel in the core.

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 liensee'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 Paragaph 55 (Attachment 22) of the DIQ dated September, 1983 or as modified in accordance with 10 CFR 75.11(c). Similar inventory data for required material control and accounting repcrts not generated as a result of a physical inventory, may be obtained from the licensee's records.

3 San Onofre -

IAEA Safeguards

Facility Attachment Code 5.1.1 Nuclear loss and production to be recorded as of the date of discharge, and optionally for the whole core, every six months" means:

Nuclear loss and production will be recorded at the time of taking the core physical inventory during a refueling outage and at an interval no greater than six months.

Facility Attachment 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.

Facility Attachment Code 7.

"Inspection" means.:

Inspection or inspections as described in 10 CFR 75.42 and as con ducted by duly authorized representatives (inspectors) of the Inter national 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 inspection effort is applied. "30 man-days per year if one refueling occurs" means:

The anticipated IAEA inspection effort under ordinary circumstances.

4 San Onofre -

IAEA Safeguards

Facility Attachment Coes*7.4.2 and 7.4.3

."Verification of the inventory, i.e., by item counting and identification" means:

The IAEA inspection effort may include the verification of all, or any portion of, the licensee's SNM inventory (fuel assemblies in the core are subject to verification only during refueling and not at any other time).

The IAEA's inventory verification procedures may include confirma tion 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.

Facility Attachment Code 7.10 The specific facility health and safety rules and regulations to be observed by the Agency's (IAEA) inspectors, as specified in Paragraph 54 of the design information as of August 22, 1983, provided by theUSA 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 view 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..

5 San Onofre -

IAEA Safeguards

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 qualified facility personnel at times deemed appropriate by the licensee.

3. TERMINATION:

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-10 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-10 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.

6 San Onofre -

IAEA Safeguards

4044W D#0017 Text prepared on:

1985-01-04 Date of entry into force: JUN 1 5

Safeguards Agreement under NPT between the USA and the IAEA Subsidiary Arrangements Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATIING STATIC Facility:

UXRF

/

MBA: UXRF UNIT-2 Total number of pages: 20 Page No. 1 Code General Agreement Part Reference Reference (Articles)

(Codes) 43(a)

Identification of the facility Facility identification code:

UXRF 1.1 Name, owner and operator San Onofre Nuclear Generating Station, Unit-2 (SONGS-2)

Owners Southern California Edison Company San Diego Gas & Electric Company City of Anaheim City of Riverside Operator.

Southern California Edison Company 1.2 Geographic location San Diego County, California, USA.

1.3 Postal address Southern California Ldison Compary 2244 Walnut Grove Avenue P.O.

Box 800 Rosemead, California, 91770 Telephone Nro.

(818) 1749 302.

Dc scription The power station cnnsists of one pressurized light water reactor, 3390 MW(t) gross thermal power.

Refuelling interval:

normially 12-

"months.

Number of assemblies discharged normally on

.refuelling: 60-e 10n

'Text prepared on:

9e 1-04 Date of entry Wo force: JUN 0 1 5

Facility Attachment No.

9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF /

MBA:

UXRF UNIT-2.

Page. 2 Code General Agreement Part Reference Reference (Articles)

(Codes) 1.4 (cont'd)

Nominal weight of fuel in assemblies: 414kg total U.

Maximum fresh fuel enrichment (U-235):

4.1'.

-- Number of fuel assemblies in core:

217.

Fresh fuel storage capacity:

80.

Spent fuel storage capacity:

800.

Fuel rods may be exchanged between fuel assemblies at the time of refuelling.

1.5 Maps and plans See Design Information Questionnaire (019).

2.

3.1 43, 44,

.Information on the facility 46(a)

This Facility Attachment is based on the design information as of September 1983 provided by USA.

2.1 8

Location of information Identical sets of the information provided on.

the facility are kept at the Agency, at the facility and at the USNRC Headquarters 2.2 3.1.3 45 Changes in th. desian information on the facility to be. Provided in advance (with refernce to the relovwnt parJ(3rphs. in the Design Information Questionnaire).

- Any change in the rated thermal output foir continuous operation.

(14)

• ~~~~

ir; f

t reactor area.

(10) ny change in the des ig3n o.f the reac tor fuel.

(24, 25. 27)

Text prepared on:

19t 1-04 Date of entry a force: JUN 61 1985 Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF / MBA:- UXRF UNIT-2 Page 3 Code General Agreement Part Reference Reference (Articles)

(Codes) 2.2 (contd)

Any change in the type of fuel used e.g.

introduction of mixed oxide fuel.

(22, 23, 25)

Any increase in the maximum ehrichmentsc f the fuel.

(22)

Any change in the method of iden tifying indiv'dual fu Il assemblies.

(31)

Any change of the refuelling equipment or methods.

(41)

Any change in the connection with the reactor vesse1 or its cover influencingj access to the core.

(43) introduction of new irradiation positions inside the reactor vessel.

(44)

Introduction of new loop heat removal equipment which would be required to increase the nominal rated core thermal power level.. (52)

Installation of any fuel assembly decladding or dissolution equipment.

(51) ny change in the routes of the shipping cask for irradiated fuel within the facility.

(50) 32.2 (ny chang3e in the health and safety regulations affectirng the conduct of inspection by the Agency.

(54)

Any cha4nge in the method u storace of irradiated fue] and of' th spent fuel Any charige n other parts o F the des ign information to be submitted when the chen-e has been completed.

Q.

-j

%0n1 116 1i L

i.

n.

.Text prepared on:

1 1-04 Date of entry Go force: JUN 1

Facility Attachment No.. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF / MBA: -UXRF UNIT-2 Page 4 Code General Agreement Part Reference Reference (Articles)

(Codes)

3.

Safeguards measures 3.1 29 Accountancy 3.1.1 46(b)

Material balance area and identification codes The SONGS-2 nuclear facility UXRF constitutes one material balance area, M3A UXRF.

3.1.2 46(b)

Strategic ocints which are Key Measurement 37, 38 Points (KMPs).

(For their specifications see Code 4.)

(a) For determination of nuclear material flow:

6.3 KMIP 1 -

Receipts, de-exemptions and accidental gains of nuclear material.

KMP 2 -

Nuclear loss and production.

3.5, 3.7 KMP 3 -

Shipments of nuclear material, 6.3, 7.1 withdrawals, exemptions and accidental losses.

.(b) For determination of the physical inventory:

KMP A -

Fresh fuel storage anid inspection VMP B~ -

R;actor core.

<MP C -

Sperit fuel 3toraf3e racks and spent fuel shipping casks.

KMP D -

Other loca t ions of nucloor

Text prepared on:. 191-04 Date of entry o force:

N985 Facility Attachment No.. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF /

MBA:

UXRF UNIT-2 Page 5 Code General Agreement Part.

Reference Reference (Articles)

(Codes) 3.1.3 46(c).

Physical inventory taking (PIT)

Nominal timing:

As soon as possible after the completion of each refueliing and before the reactor is closed again.

In case of prolonged shutdcown of one year or longer, physical inventory takings shall be performed every 12 months.

Fuel other than that contained in the core will be inventoried at least once per year.

Procedures:

Item counting arid identification. Preparation of an itemized inventory list for each inventory KMP.

3.2 29 Containment and Surveillance

.3.2.1 46(f),.

Strategic points for the apolication of containmemt and surveillance measures Reactor hall.

The fresh and spent fuel. storciae area Including access routes.

.2.2 73(d),(c)

Installed Aency_ nstruments an devicn (a)

Zeals to ensure the <;ontainnient of the reactor vessel; (b) Camores for s uruei 1 anrce of fuel moveerts into or out of the rct(-. Lor cn i~nL mert.

e ut i gj Lhe

r-r aiu ipent u

r

, r L2 (c)

Seals on shipping casks with spont fool (d)

S0ials on Agency oquipment.

Text prepared on:

1981-04 Date of entry o force: JUN Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility : UXRF / MBA:

UXRF UNIT-2 Page 6 Code General Agreement Part Reference Reference (Articles)

(Codes).

3.2.2 (cont'd)

If there is a need to break a seal or interfere with the operation of safeguards instruments, the Agency shall be informed in advance by the fastest means. This information shall include the (probable) date on which the operation will take place. If a seal is removed in the absence of an Agency inspector without the operator bcing abil to inform the Agency in advance, a special r-port will be prepared as specified in Code 6 3.3 6.1 11, 35 Specific provisions and criteria for termination of safeguards on nuclear material None.

3.4 6.2 36, 37 Specific provisions and criteria for exemoting nuclear material.from safoauards None.

3.5 3.7, 7.1 12(a).

Specific provisions and criteria for withdrawal of nuclear material from safeguards.

None.

Text prepared on:

1985

-04 Date of entry force JUN g J Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF /

MBA:

UXRF UNIT-2 Page. 7 L~--------- -- -- -- ---------

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KMPs for the f low of nuclear mater lal (continued)

Description of a typical l

Material fMeas.

PI Inventory I

Source data l DesciionIbasis Change l

batch item

_Rl NRIC AEAK 0 0 l

I 1.--r--l*

l I

I I

I~

2 Nuclear for fuel assemblies I One I (1), (2) As for fuel assemblies at.1 Ij Production, I fuel KMP I above;

.I3I l Nuclear Loss One fuel assenqbly.

I assem-(3) Estimated burn-up of each fuel I BQlG M I (burn-up)

I bly assembly (in MWD/tU), date of x

I I

(b r -p I0 0

discharge;

- J 0

(4) Nuclear loss of total and fissilel 3I uranium and nuclear production lI of plutonium for each fuel 00 assembly when calculated, in cluding as of the date of dis-l l

l charge.

I C x Nuclear Loss For fuel assembly One l (1), (2), (3) As above; I

I BQ1G I M I I (decay) fuel 1(4) Nuclear loss of total plutonium I I BQ2G I MI One fuel assembly.

assem-I (Pu-241 decay) for each fuel bly I

assembly when calculated, in-.

cluding as of the date of

-D C: 0 0

2L

1 16 s h I

I hpme nt.

Ia H z

&~

I0 I

3 Shipment For fuel assemblies I One I feach fuel assembly:

I fuel I

One fuel assembly.

I assem-i (1) Identification number; BQ2 I Mi bly l (2) Weights of total and fissile BQ2F I N I Il uranium for unirradiated fuel; I

l l (3) Weights of total and fissile V

0 I

urarium and total plutonium as I

0 calculated to allow for nuclear I J

loss and production for l

j*

irradiated fuel; l

(4) Burn--up and date of discharge of I irradiated fuel; I

(5) Isotopic composition if I

II I

available.

lI O0 2**0

Code 4.1.

KMPs for the I low of nuclear material (continued) l Description of a typcal I Material (Meas.I KMPI Inventory

(

Source data IDescriptionjbasisj ChanII[batch

_ tem N R 3 I Shipment for.maIl uantities of I

As (1) Weight of compound; I

Q/SOAj M I I I (cont'd) nuclear materia (each 1 ae pror I (2) Weights of total and fissile Q/50Hl M I hI I tn 0.01 effective I priate uranium and chemical compositIon.

I I

I I I kIigam j I I I

I I

II l Any number of such quanti-l I ties shipped in one

(

I I calendar month to the same I l

l recipient or, if a physical I 3I l inventory was taken during l l

l that month, separately I

I 1

before and after the time I

(

of physical inventory I

l I I I taking.

I I

I I Exemption, I

I I Accidental I

Same as for Shipment at.KMIP 3 above (0

(

I Loss, I

l Withdrawal I

0 f

z* 0* "

r r

C0 I

')

-h XM 0

Mn W

O C

O H 2 0

O

ode 4.2:

KMPs for Physical Inventory of nuclear material Description of a typical I Material IMeas.l KP Source data I Descriptionlbasisj

_-Item

_1..........

_NRC I AEA I l

A Ifor fuel assemblies One l For each fuel assembly fuel

[

One fuel assembly.

(fe II I

Oaassem-l (1) Identification number; BQIF N I C

bly I (2) Weights of total and fissile uranium BQ2F N I 0

for. unirradiated fuel; I BQ4F I N I (3) Weights of total and fissile uranium BQ4G I M I uranium and total plutonium as

.I I

calculated to allow for nuclear loss C 0 C

C II and production for irradiated fuel; I (4) Isotopic composition if available.

I

.I I

.I[II C

For fuel assemblies One I (1) Identification number; I BQlG I M I n

C fuel l (2) Weights of total and fissile uranium BQ2G I M One fuel assembly.

assem-and total plutonium as calculated to l

bly I

allow for nuclear loss and production C

I for irradiated fuel; l (3) Burn-up and date of discharqe of a /

I7 I

irradiated fuel; H Z I (4) Isotopic composition if available.

I A I For small quantities of nuclear materiall Not (1) Weight of compound; I/5A Nt B I Leach less than 0.01 effective kilogram) I appli-C-I (2) Weights of total and fissile uranium.

Q/SOH NM C,

I able 0 I Any number of such quantities.

l m

0 C=

X G.

O n

00 02 O

Text prepared on:. 19801-04 Date of entry force: JUN 0 1 1S85 Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF /

MBA:

UXRF UNIT-2 Page 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 accounting records 5.1.1 54(a),

Inventory changes (for the specifications of source data see Code 4.1 above),

time of recording Receipt (KMP 1):

Upon receipt.

Nuclear loss (uranium burn-up) and nuclear production (KMP 2):

When calculated, including upon discharge.

Nuclear loss (Pu-241 decay) (KMP 2):

When calculated, includinq upon shipment.

Shipment (KMP 3):

Upon shipment.

6.2 Exemption (XMP.3):

Upon the accounting transfer of the nuclear material.

6.3 De-exemptions (KMP 1):

Upon the accounting Lransfer of the nuclear material.

35-Accidental lots (KM1P

3)

Upon determining3 the amount of the loss.

Accidntal 3ain (I<MP I):

Upon drteriing the amount of the n

-- Withdraiwal (KMP 3):

Upon wi thdra al.

r uiiA

..Text prepared on:

198W1-04 Date of entry force:

JUN 0 1 1985 Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF / MBA:

UXRF UNIT-2 Page 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 soecifications of source data see Code 4.2 above) and time of recording For all physical inventory K!MPs:

Upon identification and counting of items during the physical inventory taking.

- Itemized list of nuclear material inventory:

Before inventory takinu.

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 Specific provisions for operatinq records 5.2.1

.56(a)

Operating data used to establish changes in the qyantities and co'mposition of nuclear material Location of each fuel assembly at any time.

Fhe relevant source data with respect to nuclear loss and production, includinu:

(a) The monthly integrated thermal power produced by the reactor; and (b)

The e-timated burn-un (in MWO/t) for eah fuel baemblY.

Date and duration of iry reactor shutdown.

Date and description of any dismantlinq operation of.a fuel assembly fur Pin exchange.

Text prepared on:

198 1-04 Date of entry o force:

JUN 0 1 Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility.

UXRF / MBA:

UXRF UNIT-2 Page 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 preparing for and in taking the phyical inventory At physical inventory KMPs:

Dates and description of the actions taken and the results obtained.

An itemized list of nuclear material inventory after 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 language of records At the facility and at the utility headquarters at Rosemead, California:

English.

5.4 51 Retention period for records Five years.

6.

10 46(d), 57 Reports system 6.1 3-4.1 61(a), 62 Specific provisions for inventory change 63 reports (ICRs)

,1.1 10 Contents Ih in.vn'tury cntr is.

to b r1eported are thos types spc ified in Code 5.1.1 bov1.

Will be completed as specified in sections 1 through 4 of Code 10, Genvral Part of the Subsidiary Arranaemnris.,

Text prepared on:

198

-04 Date of entry is force:

JUN 0 1 1985 Facility Attachment No.

9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF / MBA:

UXRF UNIT-2 Page 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 calculated, including as of the date of dischare. The element code of the initial fuel category will be used in reporting.

6.1.2 Timino 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 explaining the inventory changes May be attached to ICqs (or mailed 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 to ICRs (or mailed separately) to explain unusual inventory

• changes (such as accidental loss) or correction. They mn'y also be used to explain any other part of information included in the reports.

6.2.2 62(b)

Concise notes describing the anticinated oporationalproqramme; subject and timina of di patch Planned operations involving removal of the Agency reactor vessal seal, e.g. refuelling, fresh fuel receipts and spent fuel shipmuenL-.

To be attached to eah oO o Cod 6 33 below) and to cor the period until the end cf the ruext re fuelling.

Text prepared on:

19861-04 Date of entry 'o force: JUNa0 1 IM Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION Facility:

UXRF

/

MBA:

UXRF UNIT-2 Page 15 Code General Agreement Part Reference Reference (Articles)

Codes)

.6.2.2 (cont d)

Forecast for the next refuelling, physical inventory taking or spent fuel shipment including information about the shipment casks to be used and the extent to which these are expected to be filled.

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 orovisions 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.

6.3.2 10 Physical inventory listings' (PILs) to be attached to MBRs The batch data included in PILs will be based on the shipper's data on the initial nuclear material content of the fuel for unirradiated fuel assemblies in KMPs A and 8 and for small quantities and on operator's data for irradiated fuel assemblies in KMPs B and C.

Will be completed as specified in sections -1 through 4 of Code 10, General Part of the Subsidiary Arrangements.

6.3.3 Timin or freuency of dispatch Within 30 da'ys of thcp in venror taking under Code 3.1.3 above.

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(Codes) 6.4 3.5 66, 89(b)

Special reports 6.4.1 Specification of circumstances requiring submission of special reports (a)

Loss limits:

One fuel assembly.

(b) Changes in containment:

Physical integrity of a fuel assembly as an accounting unit is accidentally broken; Any Agency containment and surveillance device, 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 advance as provided for.

1/

6.4.2 Contents, as appropriate Date when the incident or circumstance occurred.

Description of the actions taken in order to ascertain the cause of the incident or circumstance and the magnitude of the loss.

-- Cause and features of the incident or circumstance.

Estimated amount of nuclear mLvrial which has been lost.

7.

4.2 Inspections 7

L, 82 Mde of routine inspections Intermittent.

1/ In respect of seals on shipping casks, this requirement applies only while the casks remain in the facility.

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(Codes) 7.2 78 Applicable formula and procedure for 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 routine 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;

2.

(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 scope of routine inspections under ordinary circumstances

7.4.1 General

Examination of records, verification for self-consistency ;raid corsistency with reports.

7.4.2 At inventory KMPs Verification of the inventory, e-.g. by itom counting, idenLifictin:.- and integjrity cu <ks and non-destructive meauromants.

Us

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(Codes) 7.4.3 At flow KMPs Verification of inventory changes, e.g. by item counting, identification and integrity checks, 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 surveillanc'e Observation of refuelling and spent fuel removal operations; Application, examination and removal of Agency seals used in accordance 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 Agency of equipment for independent measurements Specific arrangements for the use by the Agency of equipment to be made as the need arises.

7.6 9.4 73(a)

Duplicate and additional samoles Not relevant.

7.7 85, 86 Persons to whom a request.for any oowration or for services at the facility should be addressed

>. COY ell ft Sovi u

T.D. Mercurio t(2 ; 4

L 41/8)

30.

'z&/

.uclear Licensin3 Room 4.12 GO. 1 2244 Walnut Grove Avenue P.O. Box 800 Rosemead, Ca., 91770'

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(Codes) 7.8 Contacts at the facility B. Katz (714) 492-7700 Ext. 5-6631 San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, Ca., 92672 7.9 14, 86 Services and charges 7.9.1 Services orovided 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 the operator with charges to the Agency Means of communication (tolerphonrc2.

t.:lex, cable):

According to existing rates.

If any specific request by the Agency for services not covered above gives rise to e.xpenses fur whic h ru imbursement is reuiis t;d from the agency, the Ajency shall be rotiiec of the estimated oxpcenses before the srvice is performed.

The Agency will only rcimbursc such expenses if it has confirmed its initial request and agrec'd in writing to the amount involved.

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(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 insoectors 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 the time of entry into the facilit of a **

health and safety '4leY{

1 ap 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 personnel.

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 88(b)

A statement on the conclusions the Agency has drawn from its verification activities in respect of the facility will be made within 60 days after the end of the month in which the Agency has verified the physical inventory The statement will include, as appropriate, conclusions drawn from:

(a) Records examination;

(')

p r

o A

n y;

(c) Verification of containment and surveillance measures; (d) Verification of inventory changes; (e) Verification of material accountancy; (f) Verification of the quality and functioning of the operator's measurement system; (a) Activitipq in rpoqort of MHP

-hir nnori-e

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