ML13305A498
| ML13305A498 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/28/1983 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Baskin K, Holcombe J San Diego Gas & Electric Co, Southern California Edison Co |
| References | |
| NUDOCS 8312140244 | |
| Download: ML13305A498 (23) | |
Text
Docket No.:
50-361 NOV 2 8 1983 Mr. Kenneth P. Baskin Mr. James C. Holcombe Vice President Vice President -
Power Supply Southern California Edison Company San Diego Gas & Electric Company 2244 Walnut Grove Avenue 101 Ash Street Post Office box 800 Post Office bos 1831 Rosemead, California 91770 San Diego, California 92112 Gentlemen:
Subject:
International Atomic Energy Agency (IAEA) Safeguards Implementation at SONGS-2 By letter dated July 8, 1983, we informed you that San Onofre Nuclear Generation Station, Unit 2 (SONGS-2) had been identified by the IAEA under Article 39(b) of the US/IAEA Safeguards Agreement for the application of IAEA safeguards and requested that you provide us with the completed IAEA Design Information Questionaire (DIQ).
By letter dated August 30, 1983, you provided us with the DIQ for SONGS-2.
Utilizing the information provided in the DIQ, the enclosed draft Facility Attachment has been developed. You are requested to review it and provide us with any comments you may have within 30 days. As you know, the finalized Facility Attachment will be implemented at your facility through the issuance of a license amendment. We are looking forward to having your input on this matter, and we appreciate your cooperation in applying IAEA safeguards at SONGS-2.
Sincerely, Grigna sineby George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
Enclosure:
Draft Facility Attachment Documen t CbnYtrol-5~3:j cc:
See next page NRC PDR Attorney, OELD L PDR TMNovak NSIC ELdordan:IE PRC System JMTaylor:IE LB#3 Reading ACRS (16)
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San Onofre Mr. Kenneth P. Baskin Vice President Southern California Edison Company 2244 Walnut Grove Avenue P. 0. Box 800 Rosemead, California 91770 Mr. James C. Holcombe Vice President -
Power Supply San Diego Gas & Electric Company 101 Ash Street Post Office Box 1831 San Diego, California 92112 Charles R. Kocher, Esq.
Mr. Mark Medford James A. Beoletto, Esq.
Southern California Edison Company Southern California Edison Company 2244 Walnut Grove Avenue
.2244 Walnut Grove Avenue P. 0. Box 800 P. 0. Box 800 Rosemead, California 91770 Rosemead, California 91770 Mr. Henry Peters Orrick, Herrington & Sutcliffe San Diego Gas & Electric Company ATTN:
David R. Pigott, Esq.
P. 0. Box 1831 600 Montgomery Street San Diego, California 92112 San Francisco, California 94111 Ms. Lyn Harris Hicks Mr. George Caravaiho Advocate for GUARD City Manager 3908 Calle Ariana City of San Clemente San Clemente, California 92672 100 Avenido Presidio San Clemente, California 92701 Richard J. Wharton, Esq.
University of San Diego School of Alan R. Watts, Esq.
Law Rourke & Woodruff Environmental Law Clinic Suite 1020 San Diego, California 92110 1055 North Main Street San Clemente, California, 92701 Phyllis M. Gallagher, Esq.
Suite 222 Lawrence Q. Garcia, Esq.
1695 West Crescent Avenue California Public Utilities Commission Anaheim, California 92701 5066 State Building San Francisco, California 94102 Mr. A. S. Carstens 2071 Caminito Circulo Norte Mr. V. C. Hall Mt. La Jolla, California 92037 Combustion Engineering, Inc.
1000 Prospect Hill Road Charles E. McClung, Jr., Esq.
Windsor, Connecticut 06095 Attorney at Law 24012 Calle de la Plaza/Suite 330 Mr. S. McClusky Laguna Hills, California 92653 Bechtel Power Corporation P. 0. Box 60860, Terminal Annex Los Angeles, California 90060
-2 Mr. Dennis F. Kirsh U.S. Nuclear Regulatory Commission -
Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Resident Inspector, San Onofre/NPS c/o U. S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92672 Regional Administrator -
Region V/NRC 1450 Maria Lane/Suite 210 Walnut Creek, California 94596 Mr. C. B. Brinkman Combustion Enginering, Inc.
7010 Woodmont Avenue Bethesda, Maryland 20814
Text prepare?
nz 1983-09-21 Date of entry into force; Safeguards Agreement under NPT between the USA and the IAEA Subsidiary Arrangements Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Facility; UXRF
/
MBA. UXRF Total number of pages:
Page No.
1 Code General Agreement Part Reference Reference (Articles)
(Codes)
- 1.
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)
Owner and operator Southern California Edison Company 1.2 Geographic location San Diego County, California, USA.
1.3 Postal address P.O. Box 800 Rosemead, California, 91770 Telephone No...........
Telex No...............
1.4 Description The power station consists of one pressurized light water reactor, 339U MW(t) gross thermal power.
Refuelling interval; normally 12-18 months.
Number of assemblies discharged normally on refuelling:
72
- Nominal weight of fuel in assemblies:
kg total U.
Nominal fresh fuel enrichment (U-235) 1.5 -
3.0%.
Text prepared on:
1983-09-21 Date of entry into force:
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 2 Code General Agreement Part Reference Reference (Articles)
(Codes) 1.4 (cont'd)
Number of fuel assemblies in core:
217.
Fresh fuel storage capacity;
- 80.
Spent fuel storage capacity: 800.
1.5 Maps and plans See Design Information Questionnaire (DIQ).
- 2.
3.1 43, 44, Information on the facility 46(a)
This Facility Attachment is based on the design information as of provided by USA.
2.1 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 the Design Information on the facility to be provided in advance (vith reference to the relevant paragraphs in the design information provided.)
Any change in the rated thermal output for continuous operation. (DIQ: para. 14)
Any change in the access routes to the reactor area. (DIQ: para. 10)
Any change in the design of the reactor fuel.
(DIQ: paras. 24, 25 and 27)
- Any change of the type of fuel used e.g.
introduction-of mixed oxide fuel.
(DIQ: paras. 22, 23 and 25)
Any change in the nominal enrichments of the fuel exceeding 3.5 wt.%.
(DIQ; para. 23)
- Any change in the method of identifying individual fuel assemblies.
(DIQ; para. 31)
Text prepared on; 1983-09-21 Date of entry into force:
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 3 Code General Agreement Part Reference Reference (Articles)
(Codes) 2.2 (cont'd)
- Any change of the refuelling equipment of methods. (DIQz para. 41)
Any change in the connection with the reactor vessel or its cover influencing access to the core. (DIQ; para. 43)
Introduction of equipment for assembling or disassembling fuel assemblies (for fuel pin exchange. (DIQ: para. 28)
Introduction of new irradiation positions inside the reactor vessel. (DIQ; para. 28)
Introduction of new loop heat removal equipment which will be required to increase the nominal rated core thermal power level.
(DIQ; para. 52)
Installation of any fuel assembly dismantling, decladding or dissolution equipment.
(DIQ4 paras. 50 and 51)
Any chalnge in the routes of the shipping cask for irradiated fuel within the facility.
(DIQ: para. 50)
Any change in the health and safety regulations affecting the conduct of inspection by the Agency. (DIQ; para. 54)
- Any change in the method of storage of irradiated fuel and of the spent fuel storage capacity (DIQ: para. 48)
Any change in other parts of the Design Information to be submitted when the change has been completed. (DIQ; para
)
- 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, MBA UXRF.
Text prepared on:
1983-09-21 Date of entry into force:
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 4 Code General Agreement Part Reference Reference (Articles)
(Codes) 3.1.2 46(b)
Strategic points which are Key Measurement 37, 38 Points (KHPs).
(For their specifications see Code 4.)
(a) For determination of nuclear material flow; 6.3 KHP 1 -
Receipts, de-exemptions and accidental gains of nuclear material.
EMP 2 -
Nuclear loss and production in fuel.
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 and inspection area.
KMP B -
Fuel in the reactor core.
KMP C -
Spent fuel storage racks and spent fuel shipping casks.
IMP D -
Other locations of nuclear material at the facility.
3.1.3 46(c)
Physical inventory taking Nominal timings As soon as possible after the completion of each refuelling and before the reactor is closed again.
In case of prolonged shutdown of one year or longer, physical inventory takings shall be performed once every 12 months.
Fuel other than that contained in the core will be inventoried at least once per year.
Text prepared on; 1983-09-21 Date of entry into force:
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 5 Code General Agreement Part Ref erence Reference (Articles)
(Codes) 3.1.3(cont'd)
Procedures.
Item counting and identification. Preparation of an itemized list for each inventory KMP.
3.2 29 Containment and Surveillance 3.2.1 46(f),
Strategic points for the application of containment and surveillance measures Reactor.
The fresh and spent fuel storage areas including access routes.
3.2.2 73(d),(e)
Installed Agency instruments and devices (a) Seals to ensure the containment of the reactor vessel; (b) Camera(s) for surveillance of fuel movements into or out of the reactor containment including the fresh and spent fuel storage areas; (c) Seals on shipping casks with spent fuel.
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 being able to inform the Agency in advance, a special report will be prepared as specified in Code 6.4.1.
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 exempting nuclear material from safeguards None.
Text prepared on:
1983-09-21 Date. of entry into force:
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 6 Code General Agreement Part Reference Reference (Articles)
(Codes) 3.5 3.7, 7.1 12(a)
Specific provisions and criteria for withdrawal of nuclear material from safeguards.
None.
Code 4 Agreement References (Articles):
46(b), 55, 90 Specifications for Key Heasurement Points Code 4.1:
KMPs for the flow of nuclear material0 Description of a typical I Haterial JHeasure-I r
IoP Inventory
.ISource data IDescription Iment 1
-I I
I Change I
batch I item I NRC I IAEA Ibasis I
I I
I I
Receipts For fuel assemblies One For each fuel assembly:
I I
I fuel I
I I
One fuel assembly.
assem-(1) Identification number; I
BQ2F I N
bly (2) Weight of total and flssile 10 uranium and chemical composition I based on shipper's data.
I0 I
I __
_ I I_ _
I _
I I
I I
I I
1 1
I I
For small quantities of Not I (1) Weight of compound; QSOA N
nuclear material each appli-I (2) Weights of total and fissile QSOH Ni less than 0.01 effective cable uranium and the chemical kilogram) composition-based on shipper's II I
I I
data.
Any number of such quanti ties received in one calendar month from the ON same shipper, or, if a IIIj o
physical inventory was oI0 taken during the month, I
I separately before and after the time of physical II inventory taking.
De-exemption 0
Accidental Same as for Receipts at KHP I above n
gain III En
Code 4.1:
KHPa for the flow of nuclear material (cont'd)
Description of a typical Haterial Heasure IKHPI Inventory I
I I
Source data IDescription ment Change batch item I NRC I IAEA Ibasis I
2 Nuclear For fuel assemblies One (1).(2) As for fuel assemblies at 6
V Production, fuel KMP I above; I
I Nuclear lose All fuel assemblies assem-(3) Estimated burn-up of each fuel BQlC H
(burn-up) calculated together.
bly assembly (in HWD/tU);
I I
(4) Nuclear loss of total and fissile a
m uranium and nuclear production as calculated for each fuel assembly.
IIII I
1
- 1.
Nuclear loss For fuel One (1).(2),(3) As above; BQIG H
(decay) fuel (4) Nuclear lose of total plutonium BQ2C H
All fuel assemblies assem-(Pu-241 decay) for each fuel calculated together.
bly asaembly.
I 1 1I 1I1I 3
Shipments I For fuel assembliea One For each fuel assembly:
I Ifuel One fuel assembly.
asaem-(1) Identification number; BQ2G H
N 3 E a
bly (2) Weights of total and fisile BQ2F H
(W t
uranium for unirradiated fuel.
0 o
1 I
(3) Weights of total and fiessile oaI I
a uranium and total plutonium as calculated to allow for nuclear
>II loss and production for irradiated fuel; (4) Isotopic composition if available.
o 0
Code 4.1:
KHPa for the flow of nuclear material (cont'd)
]Deacription of a typical Material Measure-I a
a
- 0)
X IKMPI Inventory Source data IDescription Iment I.
n I
I Change batch I
item I
I RC I IAEA baale I..
11III1 I
a 3
Shipments For small quantities of Not (1) Weight of compound; QSOA H
(continued) nuclear material ec applic- )(2) Weights of total and fissile QSOHI H
less than 0.01 effective able uranium and chemical composition.
S I Ikilogram) 0 Any number of such quanti I I I
ties shipped in one I0 I I I calendar month to the same I
receipient or, if a 0
I I I
physical inventory was I I I taken during that month, separately before and afteri I
the time of physical inventory taking.
Exemption Accidental Same as for Shipments at KHP 3 above.
I loss a
O m
Withdrawal M
t o
I
-o a 0
c:
M'
~2
'0
Code 4.2:
KMPa for Physical Inventory of nuclear material Description of a typical I Material leasure-I I
W KPI I
Source data I Descriptioniment I
I batch I
item I
INRC IAEA basis A
For fuel assemblies One For each fuel assembly; B
fuel One fuel assembly.
assem-(1) Identification number; BQIF N
bly (2) Weights of total and fissile uranium for 8Q2F N
irradiated fuel; BQ2G H
V (3) Weights of total and fissile uranium and BQ4F N
0 total plutonium as calculated to allow for Q4G M
nuclear lose and production for irradiated I I I
I fuel; (4) Isotopic composition if available.
C For fuel assemblies One (1) Identification number; BQLG H
fuel (2) Weights of total and fissile uranium and BQ2G H
One fuel assembly.
assem-total plutonium as calculated to allow for bly nuclear loss and production for irradiated fuel; (3) Isotopic composition if available.
I 1-o A
For small quantities of nuclear Not (1) Weight of compouAd; B
material (each less than 0.01 applic-(2) Weights of total and fissile uranium based QSOA N
C I effective kilogram) able on shipper's data.
QSOH N, N H
D Any number of such quantities.
M 0
n
'In z
Text prepared on; 1983-09-21 Date of entry into force.
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA 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 and batch changes (for the specifications of source data see Code 4.1 above), and time of recording
- Receipt (KMP 1);
Upon receipt.
Nuclear loss (uranium burn-up) and nuclear production (IMP 2).
For fuel assemblies, as of the date of discharge,.and optionally for the whole core, every six months.
Nuclear loss (Pu-241 decay) (KMP 2);
As of the date of shipment, and optionally every six months.
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 1):
Upon determining the amount of the gain.
3.7, 7.1 Withdrawal (K10 3):
Upon withdrawal.
Text prepared on; 1983-09-21 Date of entry into force:
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA 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 specifications of source data see Code 4.2 above) and time of recording For all physical inventory KKPs; Upon identification and counting of items during the physical inventory taking.
5.1.3 54(c)
Adjustments and corrections, time of recording Shipper/Receiver difference:
Not relevant.
MJF:
Normally identical to zero.
Corrections:
Whenever errors have been found; 5.2 2.1.2 56 Specific provisions for operating records 5.2.1 56(a)
Operating data used to establish changes in the quantities and composition of nuclear material Location of each fuel assembly at any time.
The relevant source data with respect to nuclear loss and production, including:
(a) The monthly integrated thermal power produced by the reactor; and (b) The estimated burn-up (in MWD/t) for each fuel assembly.
Date and duration of any reactor shutdown.
5.2.2 56(b)
Calibrations Not required.
Text prepared on; 1983-09-21 Date of entry into force:
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 13 Code General Agreement Part Reference Reference (Articles)
(Codes) 5.2.3 56(c)
Sequence of the actions taken in preparing for and in taking the physical 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: 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) 6.1.1 10 Contents The 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.
Nuclear loss and production will be reported when calculated including at the time of discharge for irradiated fuel assemblies. The element code of the initial fuel category will be used in reporting.
Text prepared on: 1983-09-21 Date of entry into force:
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 14 Date of entry into force.
Code General Agreement Part Reference Reference (Articles)
(Codes) 6.1.2 Timing 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 each ICR (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 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 programme; subject and timing of dispatch Planned operations involving removal of the Agency reactor vessel seal, e.g. refuelling, fresh fuel receipts and spent fuel shipments.
To be attached to each MBR (see Code 6.3.3 below) and to cover the period until the end of the next refuelling.
Forecast for the next refuelling, physical inventory taking of 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.
Text prepared on:
1983-09-21 Date of entry into force.
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 15 Code General Agreement Part Reference Reference (Articles)
(Codes) 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.
6.3.2 10 Physical inventory listings (PILs) will accompany 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 KHPs A and B and for small quantities and on operator's data for irradiated fuel assemblies in KHPs 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 Timing or frequency of dispatch Within 30 days of the physical inventory taking under Code 3.1.3 above.
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;
Text prepared on:
1983-09-21 Date of entry into forces Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 16 Code General Agreement Part Reference Reference (Articles)
(Codes) 6.4.1 (cont'd)
Any Agency containment and surveillance device, referred to in Code 3.2.2 such as a seal or camera, is interferred with or removed in the absence of Agency inspectors, unless the Agency has been informed in advance as provided.
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 material which has been lost.
- 7.
4.2 Inspections 7.1 78, 82 Mode of routine inspections Intermittent.
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 inspection effort under ordinary circumstances An estimate 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 information provided in respect of the facility; 1/ In respect of seals on shipping casks, this requirement applies only while the casks remain in the facility.
Text prepared on:
1983-09-21 Date of entry into force:
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 17 Code General Agreement Part Reference Reference (Articles)
(Codes) 7.3
- 2.
(b) The continued validity of the information (cont'd) 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 there shall normally be one refuelling a year and no irradiated fuel shipments at this time; and or (d) That if shipments were made that there would be a means of correlating the identity and number of fuel assemblies in the spent fuel pond at the reprocessing plant.
25 man-days per year if one refuelling occurs.
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 and consistency with reports.
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 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.
Text prepared on:
1983-09-21 Date of entry into force:
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 18 Code General Agreement Part Reference Reference (Articles)
(Codes)
.7.4.4 At strategic points for containment and surveillance (fuel building, fuel handling and storage area and access routes thereto.
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.
7.6 9.4 73(a)
Duplicate and additional samples Not relevant.
7.7 85, 86 Persons to whom a request for any operation or for services at the facility should be addressed Telephone No.
Telex No..........................
7.8 Contacts at the facility Same as Code 7.7.
7.9 15, 88 Services and charges 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.
Text prepared on:
1983-09-21 Date of entry into force.
Facility Attachment No. 9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 19 Code General Agreement Part Reference Reference (Articles)
(Codes) 7.9.1(cont'd)
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 (telephone, telex, cable);
According to existing rates.
If any specific request by the Agency for services not covered above gives rise to expenses for which reimbursement is requested from the Agency, the Agency shall be notified of the estimated expenses before the service is performed. The Agency will reimburse such expenses if it has confirmed its initial request and agreed in writing to the amount involved.
7.9.3 Mode of reimbursement of the expenses charged to the Agency By check, 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 the design information as of.......
provided by the USA, and all applicable parts of 10 CFR Part 20, supplemented by entrance briefings at the time of entry to the facility.
Text prepared on:
1983-09-21 Date of entry into force.
Facility Attachment No.
9 SAN ONOFRE NUCLEAR GENERATING STATION UNIT-2, USA Page 20 Code General Agreement Part Reference Reference (Articles)
(Codes)
- 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; (b) Reports to the Agency; (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; (g) Activities in respect of MUF, shipper/
receiver differences and/or losses.