ML20237G323
| ML20237G323 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/24/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G324 | List: |
| References | |
| NUDOCS 8709020202 | |
| Download: ML20237G323 (28) | |
Text
.-
muc
/
oq'o UNITED STATES
["
' ~g g
NUCLEAR REGULATORY COMMISSION i
e K WASHINGTON, D. C. 20555 4,
,o PUBLIC SFDVICE ELECTRIC & GAS COMPANY j
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE o.bPR-70
~
e 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been
{
satisfied.
2.
Accordingly, Facility Operatino License No. DPR-70 is hereby amended by adding paragraph 2.I. to read as follows:
8709020202 870824 ADOCK0500g2 DR o
i
- I.
IAEA SAFEGUARDS 1.
INCORPORATION OF FACILITY ATTACHMENT:
Pursuant to 10 CFR 75.8, NRC License No. DPR-70 is hereby amended to incorporate by reference Codes 1. through 7. of Facility Attachment No. 13 da'ted October 1, 1986, to the US/IAEA Safeguards Agreement.
2.
FACILITY ATTACHMENT CODE 2.2 Notification of the changes referred to in Code 2.2 of the facility attachment is the responsibility of the operating facility.
They can be notified to the NRC with a Concise Note (D0E/NRC Form 740M) or a letter. Notification is required 70 days prior to'The event.
3.
FACILITY ATTACHMENT CODE 3.1.3 & 5.1.2 & 5.2.3 The itemized lists of nuclear material to be provided to the IAEA as of cycle shutdown date prior to physical inventory taking are:
1.
A complete list of fuel assemblies by ID number at all locations.
2.
Reactor.and fuel storage maps showing location of fuel by l
ID number at time of physical inventory taking.
3.
A list, by batch, of any other accountable nuclear material, l
e.g., start-up sources, samples.
4.
FACILITY ATTACHMENT CODE 3.2.2 l
Please refer to NRC letter dated May 27, 1986, to Mr. C. A.
McNeill from Steven A. Yarga which spells out timeliness and procedures for notification under this code.
5.
FACILITY ATTACHMENT CODE 5.1.1 & 6.1.1 The statement "when calculated" means at least as often as required on page 2 of NUREG/BR-0006 Revision 2 or more often, j
at your option, if you calculate burn up more than every six l
months.
6.
FACILITY ATTACHMENT CODE 6.1.1 & 6.1.2 The phrase "as specified in relevant paragraphs of Code 10" is a requirement on the U.S.
All of the paragraphs in the US/IAEA
.. 1 Agreement that require a report from the U.S. to the IAEA based on source data from an operating facility have been incorporated into NUREG's BR-0006 and 0007 so that the NRC may collect the l
needed data for transmittal to the IAEA.
PSEAG should follow these NUREGs precisely in reporting inventory changes.
A complete response to the reporting instructions in the NUREGs l
will satisfy the requirements specified in Code 10.
I 4
7.
FACILITY ATTACHMENT CODE 6.2.2 The phrase " precise forecasts" means best estimates.
These required concise notes should be dispatched to the NRC at least l
40 days in advance of a projected 6 month operational programming.
j 8.
FACILITY ATTACHMENT CODE 6.3.1 & 6.3.2 See response to Code 6.1.1 and 6.1.2 above.
9.
FACILITY ATTACHMENT CODE 7.9 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 October 10, 1986, provided by the U.S.A. mean:
l 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 situatioH that has occurred at the facility since the inspector's last visit to the facility.
The briefing will be of a short duration, not to exceed 30 j
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 I
facility of health and safety rules and ad hoc rules as might i
be required in view of a special situatioR that has occurred at the facility.
The briefing will be of %n 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 i
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.
.. 10. 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 Agreemen_t.
The IAEA Safeguards License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License DPR-70 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 1. through 6. of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeauards License Conditions to NRC License No.
DPR-70 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.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Facility Attachment Date of Issuance: August 24, 1987 Previously concurred *:
PDI-2/LA*
PDI-2/PM*
AG PDI-2/D M0'Brien DFischer:ca
//1' 4*h4h Butler 08/13/87
.08/13/87
//(
7-g/21 /87
{l
. 10.
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 DPR-70 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 1. through 6. of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeauards License Conditions to NRC License No.
DPR-70 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.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Facility Attachment Date of Issuance: August 24, 1987 1
Previously concurred *:
M0'Brien DFischer:ca gh' 4 44h l PDI-2/Df PDI-2/LA*
PDI-2/PM*
0G Butler 08/13/87 08/13/87
//{
g/2l/87
/
6
. 10.
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 Sc"aguards Agreement. The IAEA Safeguards l
License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License DPR-70 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 i
under Article 2(a) of the Protocol, provisions equivalent to l
Codes 1. 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.
DPR-70 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/lAEA Safeguards Agreement are terminated.
3.
This license amendme[it is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Walter R. Butler, Director l
Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation 1
Attachment:
l Facility Attachment Date of Issuance: August 24, 1987
\\
l
UNCubSlHED
. Text pr: pared cn 1986-09-24 Data of cntry into fcece:
1986-10-01 Safeguards Agreement between USA and the IAEA
~
Subsidiary Arrangements Facility Attachment No. 13 SALEM NUCLEAR CENERATING STATION, UNIT 1 Facility Code: UXHF / MBA Code: UXHF Total number of pages:
19 Page No. 1 of 19 pages General Agreement Code Part Reforence e A "fS I A 17 e s (1 11 t 1 ' l "
A Reference (Articles) on
. U
. Th T J g J u til J.t Th.
~
(Codes) 1.
43(a)
Identification of the facility Facility identification code: UXHF 11 D
-- Sales Nuclear Generating Station Unit 1 (SNGS 1)
Owner and operator Public Service Electric & Gas Co.
1.2 Geographie location Salem County, New Jersey, USA 1.3 Postal address Public Service Electric and Gas Co.
Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 1.4 Description The power station consists of one pressurized light water reactor.
Pin removal or exchange is not normally performed.
Main design features are ai follows:
- Peactor thermal output:
3411 MW(th)
- Refuelling intervel: normally 15-19 months
- Number of fuel assemblies in the reactor core: 193
- Fresh fuel storage capacity:
72
- Spent fuel storage capacity:
1170
[0609W]
UNClASS :D Text prepared en 1986-09-24 Dato of cntry into forco:
1986-10 4 1 Facility Attachment,No. 13 SALEM NUC1. EAR GENERATING STATION, UNIT 1 Facility. Code: UXHF / MBA Code: UXHF Page No. 2 of 19 pages General Agreement Code Part Reference Reference (Articles)
I3 0
i0 0 Ill I L A (Code s)
"I'"
JU'I' J'*ll C 1.4 (continued)
- Nominal weight of nuclear material in an assembly:
462kg
- Maximum fresh fuel enrichment (U-235):
3.80 w/o
- Number of assemblies nonnally discharged on refuelling:
72-117 1.5 Maos and plans See Design Inforination Questionnaire (DIQ).
~
2.
3.1 43, 44 Infocustion on the facility 46(a) l This facility ettachment is based on the design infonnation dated to October 1985, and the design information supplement provided in September 1986.
2.1 8(c)
Location of inferination
?
Identical sets of the infonnation 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 information on the facility to be provided in advance With reference to the relevant paragraphs of the Design Information Questionnaire
- Change in the rated thermal output for continuous operation by 20% or more; (14)
I
- Change of the type of fuel used, e.g.
l introduction of mixed on.ide fuel for test purposes or for routine use; (22, 23, 25)
- Change of the maximum enrichment of the fuel; (23)
- Change in the design of the reactor fuel; (24, 26, 27)
- Installation of equipment for pin removals or enchange in assemblies for test purposes or for routine use; (13, 28)
- Change in the method and/or procedure of I
identifying individual fuel assemblies; (31)
I i
- Change in the methods and/or equipment for refuelling snd/or for handling of irradiated j
fuel; (41)
Test prepared en 1986-09-24 Dato of entry into fcreo:
1986-10-01 Facility Attachment No. 13 SALEM NOCLEAR GENERATING STATION, UNIT 1 Facility, Code: UXHF / MSA Code: UXHF page No. 3 of 19 pages l
General Agreement Code Part Reference SA""iAn"0 i"L" "l''
Reference
( Article s) gn
, g
, ry g
, g
,.1 1
,N.
(Codes) 2.2 (continued)
- Change influencing the access to the reactor vessel and/or its cover:
(43)
- Change in the number of fuel assemblies, control elements, dummy assemblies and/or irradiation positions inside the reactor vessel:
(44)
I
- Change in the method of storage of irradiated fuel and/or in the spent fuel storage capacity; (40)
- - Installation of any dismantling, decladdirs or dissolution equipment:
(13, 20, 51)
- Change in the nuclear material accountancy and control procedures:
(55)
- Change in the access routes to the reactor area:
(10)
- Change in the shipping containers and/or the routes followed by irradiated fuel within the facility; (50)
- Change in the health and safety rules and procedures affecting the conduct of inspection:
(54)
Any change in other parts of the design information to be submitted when the change has been completed.
3.
Safeeuards measures 3.1 29 Accountanev 3.1.1 46(b)
Material Balance Areas and their identification codes. The Salem Nuclear Generating Station Unit 1, UXHF, constitutes one material balance area, UXHF.
3.1.2 46(b)
Strategic points which are Key Measurement Points 90(K)
(KMPs), (for their specifications see Code 4.)
(a) For determination of nuclear material flow:
KMp 1 - Receipts, accidental gains and de-exemption of nuclear material; h
- :D R.
~
q Text prepared en 1986-09-24 Data cf cntry into f8rco:
1986-10-01 i
Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility, Code: UXHF'/ PWA Code: UXHF Page No. 4 of 19 pages 1
General Agreement
- Uu ! g
'l Code Part Reference B I
" " 't i fl
" e i"Lt" '"
Reference (Articles)
GM
. J IC 0. J
,1 1
in, (Codes) 3.1.2 (continued)
KMp 2 - Nuclear loss (bump) nuclear production and category change in fuel discharged from the reactor; nuclear loss (Pu-241 decay);
KMP 3 - Shipments of nuclear material, withdrawals, exemptions ard accidental losses; (b) For determination of physical inventory:
l
^-
KMP A - Fresh fuel storage and inspection area; l
KMP B - Reactor core; j
KMP C - Spent fuel storage racks and spent fuel shipping casks; KMP D - Other locations of nuclear material at the facility.
3.1.3 46(c)
Physical inventory taking Nominal timing:
As soon as possible after completion of each i
refuelling and before the reactor is closed again.
In cases of prolonged shutdowns of one year or longer, PITS shai.1 be performed once every twelve months.
Procedures:
Item counting and identification.
Preparation of itemized list of nuclear material including identification number, material description, quantity of nuclear material and location of each item for each inventory KMP.
3.2 29 Containment _and survelliance 3.2.1 46(f)
Strategic points for application of containment 90(S) and surveillance measures
- Reactor hall including reactor vessel;
- Access routes to and from the reactor hall and spent fuel pool;
- Fresh and spent fuel storage areas;
- Any other points that might be mutually agreed.
n
3 0. ASS E D Tcat prepared cn 1986-09-24 Dato of entry into force:
1936-10-01 Facility Attachment No. 13 SALEM NUC1. EAR GENERATING STATION, UNIT 1 Facility, Code: UXHF 7 MB A Code: UxHF Page No. 5 of 19 pages General Agreement
~
Code Part Reference OAE"i l15
" e i fL'"
" U" i l Reference (Articles)
Ort
. J
. fl 1
9 JL4 1
.1
,il, (Codes) 3.2.2 73(d)
Installed Agency instruments and devices I
73(e)
(a) Seals to ensure the containment of the reactor vessel; (b) Cameras for surveillance of fuel movements into or out of the reactor vessel, the reactor containment and the fresh and spent fuel storage areas;
{
s l
(c) Seals on shipping casks with spent fuel and other containers as applicable;
^'
(d) Seals on Agency instruments and devices; (e) Seals on containers with fuel assemblie's received at the facility; (f) Seals on the reactor containment building (e.g.
o equipment hatches).
If there is a need to break a seal or interfere with the operation of surveillance devices, the Agency shall be informed in advance and by the fastest means. This information shall include the (probable) date on which the operation will take place.
3.3 6.1 11, 35 Specific crovisions and cr teria for termination of i
safeguards on nuclear material None.
3.4 6.2 36, 37 Specific provisions for exempting nuclear material l
from saf eguards l
l l
None.
3.5 3.7, 7.1 12(a)
Specific provisions and criteria for withdrawal of nuclear material from safeguards None.
.A
yv v v - -- -
gg y y-u; v v, y Teat prepared on 1906-09-24 Date of entry into forco:
1986-1 M 1 Facility Att:chment No. 13.
SALEM NUCLEAR GENERATING STATION, UNIT 1 I
Facility Code: UXHF / PGA Code: UXHF l
Page No. 6 of 19 pages l
I l Code 4.
l l Agreement References (Articles): %W M '
l lsp deifications for New Measurement Points l
l l
l Code 4.1: KMPs for the flow of nuclear material l
)
l l
lxl l
Description of a typical l
l Mat. -lMeas.j j
lMl Inventery l l
Source data lDeser lbesisl l P_l Chance l
batch l ites l l Code l
l ll l
l l
l l
l l1l Receipts of l For fuel assemblies:
l One l For each fuel assemb1v: ~l BQ2F l N l l l nuclear l
l fuel l l
l l
l l material l One fuel assembly.
lasseerl 1) Identification number;l l
l ll l
l bly l 2) Ideights of total and l l
l ll l
l l
fissile uranium, and l
l l
~
ll l
l l
the chemical composi.l l
l ll l
1 l
tion; I
l l
l l l
l l based on shipper's data, i l
l l l l
l l
l t
l ll l
l l
l l
l l l l For small avantities of l As l For each batch:
l As l N l ll l nuclear material (each lappro-l lappro-l l
l l l 1ess than 0.01 effective lpriatel 1) Ideight of compound; lpriatel l
3 l l l kiloeram):
l l 2) Ideights of total and l l
l 1l l
l l
fissile uranium, and l
l' l
l l l A number of such quanti-l l
of plutonium, and the l l
l l l l ties received in one l
l chemical composition; l l
l l l l calendar month from the l l based on shipper's data. l l
l l l l same shipper or, if a.
l l
l l
l j
l l l physical inventory was l
l l
l l
l l l l taken during the month, l
- l l
l l
l l l separately before and l
l l
l l
l l l after the time of physi-l l
l l
l l l l cal inventory taking.
l l
l l
l l l l
1 l
l l
l l l l
l j
l l De-enemption,l I
l l l Accidental l
Same as for Receipts at KMP 1 above.
l l l gain l
l l_I I
1 Il 1
I l
l l
l l2l Nuclear l For fuel assemblies:
l One l For each fuel assembly l BQ1G l M l l l production, l
l fuel l-l l
l l l Nuclear loss l One fuel assembly.
lassem-l 1)-2) As for fuel assen-l BQ4G l M l l l (burn-up) l l bly l
hiles at KMP 1 above; l l
l 4
l1 l
l l 3) Date of discharge; l
l l
l1 1
1 l' 4) Estimated burrr up of l l
l ll l
l l
oach fuel assembly l
l l
l l l
l l
(in Pedo /tu);
l l
l ll l
1 I
I 1
l m
- ~ - _ _
Text' prepared en 1996-09-24 D:to of cntry into fccco:
1906-10 01 Fccility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code:,UXHF / MBA Code: UXHF Page No. 7 of 19 pages l
l l Code 4.1: Nuclear Material Flow KMPs l
g lKl l
Description of a typical l
l Mat.
(Meas.l lMl Inventory l l
Source data lDescr.l basis l lPl Chanes l
batch l item l l Code l
l l l l
l l
l l
l l2l Nuclear l
l l 5) Nuclear loss of total l l
l l l production, l
l l
and fissile uranium l
l l
l l Nuclear loss l l
l and nuclear production l l
l l l (buin-up) l l
l of total plutonium l
l l
ll l
l l
when calculated, j
l l
l l [ continued]
l l
l including as of the l
l l
l l l
l l
date of discharge. y l l
l l _l l
l l
l l
l l l l
l l
l l
l l l Category l For fuel assemblies:
l One l 1) Identification number;l BQ1G l M l l l change l
l fuel l 2) Date of discharge; l
l l
l l l One fuel assembly lassem-l 3) Weight of total and 0
l l
ll l
l bly l
fissile uranius as of l l
l l l l
l l
the date of discharge. l l
l l l l
l l
l l
l l l l
l l
l l
l l l Nuclear loss l For fuel assemblies:
l One l For each fuel assemb!v:
l SQ1G l M l l l(Pu-241 decay)l l fuel l l
l l
l l l One fuel assembly.
lassen-l 1)-2) As for fuel assem-l SQ4G l M l l l l
l bly l
blies at KMP 1 above; l l
l l l l
l l 3) Date of discharge and l l
l l l l
l l
shipment; l
l 1
l l l
l l 4) Nuclear loss of total l l
l l l 1
l l
plutonium (Pu-241 l
l l
l l l
l
.l decay) for each fuel l
l l
l l l
l l
assembly when calcu-l l
l l l l
l l
lated, including as ofi j
l Il l
l l
the date of shipment. l l
l l
l l l
l l
l l
l 1l 1
l l
l l
l l3l Shipment of l For fuel assemblies:
l One l For each fro,sh fuel l BQ2F l N l
i l l nuclear l
l fuel l assembiv:
l l
l i
l l material l One fuel asses 41y.
lassem-l l
l l
l l l
l bly l 1) Identification number;l l
l l l l
l l 2) Weights of total and l
l l
l l l
l l
fissile uranium, and l
l l
l l l
l l
the chemical composi-l l
l l l l
l l
tion.
l l
l l_l l
l l
l
-l l
jf If fuel assemblies discharged from the reactor are returned to the core, the values for nuclear production and nuclear loss which had been recorded for these assemblies shall be kept.
gg t
,j Text prepared en 1986-09-24 Dato of entry into forco:
1936-1 M 1 Fccility Attcchment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code:,UXHF / MSA' Code: UXHF Page No. 8 of 19 pages l
l Code 4.1: Muclear Meterial Flow xMPs l
'l I
lxl l
Description of a typical l
l Mat.
lM6as.l lMl Inventory l l
Source data lDescr.lbasis]
lpl Change l
batch l ites l l Code l
l l l
_ l l
l l
l l
l3l Shipment of l For fuel assemblies:
l One l For each irrad.iated fuel l BQ2G J M l l l nuclear l
l fuel l assembly:
l l
l l l meterial l One fuel assembly, lassen-l l
l l
l l l
l bly l 1) Identification number;l l
l ll l
l l 2) Date of discharge; l
l l
l l [ continued] l l
l 3) Burn-up (PWO/tu);
l l
j l l l
l l 4) Weights of total and l
l l
ll l
l l
fissile uranium and l
l l
l l l
l l
of total plutonius, l
l l
l l 1
l l
calculated as of the l l
l ll l
l l
date of discharge, andl l
l l l l
l l
corrected for Pu-241 l
l l
ll l
l l
decay between the datel l
l ll l
l l
of discharge and the l
l l
l l l
l l
date of shipment; I
l l
l l l
l l 5) Isotopic composition l l
l 11 1
l l
of uranium and pluto-l l
l l l l
l l
nium calculated for l
l l
l l l
l l
each assembly as of l
l l
l l l
l l
the date of discharge,l l
[
ll l
l l
and corrected for l
l l
l l l
l l
Pu-241 decay between l
l l
l l l
l l
the date of discharge l l
l l l l
l l
and the date of ship-l l
l 1l l
l 1
ment.
l l
l 1l l
1 l
I I
l 1l I
I l
l l
1 l l l For small quantities of l As l For each batch:
l As l
N,
[
l l l nuclear material (each lappro-l lappro-l M l l l l less than 0.01 effectivelpriatel 1) Weight of compound; lpriatel l
l l l kilogram):
l l 2) Weights of total and l
l l
11 I
l l
fissile uranium, and l
l l
l l l Any number of such quan-l l
of plut6nium, and the l l
l 1l l tities shipped in one l
l chemical composition. l l
l l l l calendar month to the l
l l
l l
l l l same recipient or, if a l l
l l
l l l l physical inventory was l
l l
l l
l l l taken during the month, l l
l l
l l l l separately before and l
l l
l l
l l l after the time of physi-l l
l l
l l l l cal inventory taking.
l l
l l
l l l l
l l
l l
l l l l
l 1 l Exemption l
l ll l
l l
l l l
Same as for Shipment at KMP 3 above.
l l
l l l Accidental l
l l
j l loss /
l l
l l Withdrawal l
l 0 11
___ __ A n
s, s
- ~
Tex"tpreparhor 198009-24 Date of cntry into forco:
1936-10 01
\\
Fer;fjityAtt:chmentNo.13 SALEM NOCLEAR GENERATING STf. TION, UNIT 1 Frsility Code: UXHF / MA Code: UXHF 1
Page Ns, 9 of 19 pages
- h,i l
v 's I
l Corfe 4j: 4tds for the physical inventory of, nuclear material l
3
-. 3 l
lKl Descript. ion ct' a typical l
l Mat.
l Meas.l lnl l
Source data lDescr.l basis l lf l.' t batch
_.l item _l l Cods l
l l l
'l l
l 1
l 4
s l One l G r each fuel assembly:
l 891F l N l lAl ? - ru,3,l_,,9,n,s, omb l i e s :
ll l fuel l" l BQ2F l N l l l One fuel assembly.
lassen-l As for fuel assemblies at l
l l
lj\\
l bly l KMP 1 ab6 e.
l l
l l_l-f_
._I l _._
.I l
l ll l
1 l
l l
l lBl For fuel essemblies:
l Ons l As for fuel assemblies at KMP 1l SQ4F l N l l l l fuel J. for unieradiated fuel or as forl DQ4G l M l b
l l One fue((assembly.
lansere-l fuel assemblies at KMP 2 on l
l l
ll l bly l calculated values for l
l l
~
s'l4 l l
l irradiated fuel.
l l
l n
A l _f,E l
l 1
I l
ll l
l l
l l
lCl For fuel asthe,,,blies:
l One l For each fuel assembiv:
? BQ1G l M l l l 3
l fuel l l BQ2G l M l l l One fuel eensbly.
lasssa-l 3) Identification number; l
l l
ll M*.
l bly l 2) Weights of total and fissile l l
l l
ll l
l uranium and of total pluto-l l
l ll k
l l
nium calculated as of the l
l l
l l l
l date of discharge, and l
l l
l l l
l corrected for Pu-241 decay l
l l
l l
\\
l l
between the date of dis-l l
l ll l
l charge and the date of l
l l
ll l
l shipment; l
l l
l l l
l 3) Date of dischw ge; l
l l
l l l
l 4) Burn-up (PldO/tU);
l l
l ll l
l 5) Isotopic composition.
l l
l
,j n
,s l _ l __
l l
_l 1
I l l l
l l
l l
l Al For small cuantities of nuclear l As l For each batch:
l As l
N.
l lM maturial (each less than 0.01 lappro-l lappro-l M l
lCl vffective kiloeram):
lrriatel 1) Weight of compound; lpriatel l
f lDb l
l 2) Weights of total and fissile l l
l l l' Any number of such quantitiss,
l l
l l
l l l.__;.
I I
I I
l b\\
n A
' Text prepared en 1986-09-24 00to of entry into forco:
1986-1 N 1 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility. Code: UXHF'/ MBA Code. UXHF Page No. 10 of 19 pages General Agreement Code Part Reference p3**i'Ar)=0 i(1 L f *L "' A Reference (Articles) 9 5
, r J
. ft h
= d JU 1I
- Ib fl -
(Codes) 5.
tocords systes o t'ht' 5.1 Mi y), O Specific provisions for accountine records 5.1.1 kh)
Inventory changes (for the specifications of source p) data see Code 4.1 above), time of recording.
- Receipt:
Upon receipt.
- Nuclear loss (burn-up), nuclear production and category change:
When calculated, including upon discharge. 2/, 3/
- Nuclear loss (Pu-241 decay):
When calculated, including upon shipment.
4
- Shipment:
Upon shipment.
f a
6.3,6.2
- Exemption /de-exemption:
Upon accounting transfer of the nuclear material.
- Accidental loss / gain:
l Upon establishment of the amount of material lost / gained.
3.7,'7.1
- Withdrawal:
Upon withdrawal.
5.1.2 2.1
%b)
Measurement (item counting and identification)
'~
results used for determination of the physical inventory (for specificat, ions of source data see Code 4.2 above), time of recording.
- Itemized list of nuclear material quantities ~ on inventory for each inventory KMP:
Upon identification and counting of items during the physical inventory taking.
- Itemized list of nuclear material inventory identifying changes since the physical inventory taking:
Before inventory verification.
l l
l 2/ Fuel removed from the reactor shall be considered as discharged if it remains out of the core after the routine refuelling shutdown is completed.
1/ If fuel assemblies discharged from the reactor are returned to the core, l
m
_n_
n_
n-__
_~o_
m
_n-_-
n_--
~, - -
1 UK,UGSARED 1
Text prepared cn 1985-09-24 D3to of entry into fereo:
1popggg Fa:ility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility. Code: UXHF / nBA Code: UXHF Page No. 11 of 19 pages General Agreement Code Part Reference O A E i ' ' A 5
' 0 '
i "' ' CT 'l * [ "" 1 Reference (Articles) gn,
,J nn,9
.J<1 d
1 n.
(Codes) 5.1.3 M*
g)
Adjustments and corrections, time of recording.
- Shipper / receiver difference:
Normally not relevant.
l
- MUF:
)
Normally identical to zero.
l l
- Corrections:
whenever errors have been found, with specific l
reference to the entry being corrected.
l 5.2 g.2 14 Specific provisions for operatine records 5.2.1 Sigy)
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 therieel power produced by the reactor; and l
l (b) The estimated burn-up (in PbO/t of uranium) for each fuel assembly;
- Date and duration of any reactor shutdown;
- Date and nature of the use of fuel handling and transport equipment, 5.2.2 g
Calibrations Not required.
5.2.3 M c)
Sequence of the actions taken in preparing for and in taking the physical inventory
- All physical inventory KMps:
Dates 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.
l l
l l
1 gy Text prepared cn 1996-09-24 Disto of entry into force:
1986 10.o1 Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility, Code: UXHF'/ MBA Code: UXHF Page No. 12 of 19 pages General Agreement Code Part Reference O A "'
S 15"6 in L
f L'T A
Reference (Articles)
.. a 3, tw '
g g
,g g g g,,g
, g jyai 4
(Codes) 5.2.4 N'
Actions taken in order to ascertain the cause and magnitude of any accidental or unmeasured loss
- Dates and de.cription of the actions taken and the results obtained.
5.3 R
Location and lanounes of records At the facility in English.
f 5.4 pt Retention period for records
~
Five years.
6.
!,gorts svetae YoY 6.1 3.4.1 8),
Specif f e provisions for Inventory Chance Reports gfS (ICRs)
D 6.1.1 10
%)
Contents The recorded entries to be reported are those types specified in Code 5.1.1 above.
ICRs will be completed as specified in the relevant paragraphs of Code 10, General Part. Nuclear loss, nuclear production.and category change for irradiated fuel assemblies will be reported when calculated including as of the date of discharge.
6.1.2 6Y(a)
Timing or frequency of dispatch As soon as possible and in any event within 30 days after the end of the month in which inventory changes specified in Code' 5.1.1 occurred or were established.
6.2 3.4.1 42 Specific provisions for concise notes l
l 6.2.1 62(a)
Concise notes esplaining the inventory changes
- To be attached to ICRs containing data on nuclear loss and production; they are to state the l
burn-up in Phl0/t of initial U for each fuel l
assembly discharged;
UNGUNititu
' Test prepared on 1986-09-24 Date of entry into force:
1906-10.01 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Attachment No. 13 Facility Code: UXHF / MBA Code: UXHF Page No. 13 of 19 pages General Agreement Code Part Reference Reference (Articles)
- j, j
g (Codes) 6.2.1 (continued)
- To be attached to ICRs to esplain unusual inventory changes (such as accidental loss) and corrections. They may also be used to explain any other part of information included in reports.
6.2.2 Concise notes describing the anticipated operational programme; subject and time of dispatch.
- Planned operations involving refuelling, fresh fuel receipts and sporet fuel shipments:
To be attached to each MOR (see Code 4.3.3 below) o
~
and to cover the period until the end of the nest refuelling, to be updated every six months.
- Precise forecasts for:
a) Date of the nest refuellirwg, physical' inventory taking including date when seals are espected to be removed from the reactor; and b) Spent fuel shipments, including information about the shipping casks to be used, the
+
estent to which they are espected to be filled:
to reach the Agency at least 30 days in advance, subsequent changes as soon as known.
6.3 3.4.2 61(b),65 Soecific orovisions for Material Balance Rooorts (MSR) 6.3.1 10 65, 90(M)
M8R contents The consolidated inventory changes to be reported are those types specified in Code 5.1.1 above.
MOR: will be completed as specified in relevant paragraphs of Code 10, General Part.
6.3.2 10
%' 90(M)
PIL contents
- Physical inventory listings (PILs) based on the results of physical inventory taking, to be attached to MSRs. The batch data included in PILs will be based on the shipper's data on the initial nuclear material content for the fuel for unieradiated fuel assemblies or on the operator's data for irradiated fuel assemblies. PILE will be completed as specified in relevant paragraphs of Code 10, General Part.
A
U3CLASSiflED Text pr: pared an 1986-09-24 Dato of entry into fereo:
1936-1 H 1
~
Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility ~ Code: UXHF / MBA Code: UXHF Page No. 14 of 19 pages General Agreement l
Code Part Reference pj pt,[7Pp 11 p L
p1 a
Reference (Articles) grU Iw W W rn m W J 'J 11 a<='lln.
(Codes) 1 6.3.3 M
Timing or fraquency of dispatch:
- As soon as possible and in any event within 30 days af ter the physical inventory taking under Code 3.1.3 above.
6.4 3.5.1 Special reports 6.4.1 Specification of incidents or circumstances requiring ss mission of special reports
' ' (a) Losses:
One or more fuel assemblies; i
(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 is interfered with or removed in the absence of Agencyinspectors,unlesstheAggeyhasbeen informed in advance as provided.-
I 6.4.2 Contents
- Date when the incident occurred or circumstances were established:
- Description of the actions taken in order to ascertain the cause of the event and to establish the magnitude of any loss of nuclear material:
- Cause and features of the incident or circumstances; of In respect of seals on shipping casks, this requirement applies only while the cask remains in the facility.
A
\\
Text prepared en 1986-09-24 D:ta of entry into farco:
1936-10-01 j
a i
Facility Attachment No. 13 SALEM NUCt. EAR GENERATING STATION, UNIT 1 Facility Code: UXHF / MBA Code: UXHF Page No. 15 of 19 pages l
General Agreement Code Part Reference en="iIAM
=p i f LI ? L '"
L A"
Reference (Articles) gg
, 3 j n i)
,,J J t. i t,
< w 1
M,.
(Codes) 6.4.2 (continued)
- Estimated amount of nuclear material which has been lost.
7.
4.2 jpD" Inspections 7.1 79,3& '
Mode of routine inspections Intermittent.
7.2 Tkb' Apolicable formula and procedure for determination of maximum routine inspection effort:
Article 78(a) of the Agreement j
7.3 NELPE Actual inspection effort related to routine inspection activities The actual inspection effort will be determined by the Agency on the basis of the relevant provisions of the Agreement to ensure the attainment of Agency safeguards objectives, assuming:
)
3.1 a) Circumstances at the facility to be as described in the design information referred to in Code 2. above' 1
2.
b) The continueo validity of the information on the State System of accounting for and control of nuclear material, as set out in the General Part.
7.4 75.73 Indication of the scope of routine inspections j
under ordinary cireuestances
7.4.1 General
i
- Examination of the records. verification for i
self-consistency;
- Comparison of reports and -ecords for consistency.
7.4.2 At inventory KMPs i
- Verification of the inventory by item counting, identification, integrity checks, non-destructive measurements.
- Application, examination and removal of Agency seats.
i l
i n
UNCl.ASSlHF.D
- Tcat prepared en 1986-09-24 Dato of entry into forco:
1986-10-01 SALEM WDCLEAR GENERATING STATION, UNIT 1 Facility Attachment No. 13 Facility Code: UXHF / MBA Code: UXHF Page No. 16 of 19 pages
~
~
General Agreement Ccde Part Reference e 3 "r i A1"O i" 1
" L"'J f
Reference (Articles)
Q M L J
. ft \\
. G Jt
.1 lfL.
(Codes) 7.4.3 At flow KMPs
- Verification of inventory changes by item counting, identification, integrity checks, non-destructive measurements of fresh and irradiated fuel.
l
- Application, examination and removal of Agency seals.
7.4.4 At stri.tegic points for containment and surveillance
- Application, examination and removal of Agency seals:
- Servicing and maintenance of C/S instruments and devices;
- observation of refuelling and spent fuel removal operations.
7.4.5 During interim verification of nuclear material inventory
- Item counting, identification, integrity checks,
.and NDA measurements (except material in core).
- Application, examination and removal of Agency seals.
7.5 7)(d)
Arrangements for the use by the agency of equipment for independent measurement Specific arrangements for the use of equipment to be made as the need arises.
7.6 WI,86 Persons to whom a recuest for any operation or for services at the facility should be addressed Vice President for Nuclear Public Service Electric and Gas Company 7.7 Contacts at the facility Manager - Nuclear Fuel Nuclear Department Salem Nuclear Generatirq Station, Unit 1 0
UNCLASSIED Text prepared en 1986-09-24 00te of entry into fcree:
1936-10 c1 I
O
~
Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility pode: UXHF / PSA Code: UXHF Page No. 17 of 19 pages I
General Agreement Code Part Reference O A
" E p il A M " 6
'l f L
E !" "i" 1!
Reference (Articles)
O rt
.U Uns\\,9 J i
,1 1
, f1 (Codes) 7,3 Services and chartres 7.3.1 Inspection activities Chartie
- Observation of ongoing operational l
activities.
None
- Ites counting and identification.
None 4
.._ - Reading of instruments relevant to measurements connected with source l
i and process data.
None
- NOA measurements:
j a) Calibration of NOA instruments:
None
)
l b) Verification of NOA instruments l
calibration through the use of standards.
None e
c) Agency NOA measurements.
None 1
J l
d) Personnel and equipment for handling nuclear material during j
its measurement.
None
- Records:
Examination of records including reconciliation of records and reports and establishment of updated book inventory.
None l
- Application, checking and removal of Agency seals.
None r
- Surveillance:
{
Positioning, removal and use of i
Agency's surveillance devices.
None
- Lighting, including emergency lighting to light all critical areas under surveillance.
None
- Reviewing of surveillance records.
None
- Other charges.
e Charges in connection with inspection activities not included above will be discussed as the situation arises.
~
_____________________D
s
+
UNG A531HtU Text prepared en 1986-09-24 Dato of entry into forco:
1906-10-c1
)
Facility Attachment No. 13 SALEM NUCLEAR GENERATING STATION, UNIT 1 Facility Code: UXHF / PWA Code: UXHF Page No. is of 19 pages General Agreement Code Part Reference 6 A "
"L
'Al
= 6
'l "
L
' " ""L"'!'
Reference (Articles)
QMf 3 mod =0 J
=
'l
ml 0
~
(Codes) 7.3.2 Services
- Health and safety (including e.g.
protective clothing, dosimeters).
edone
- Office space.
None
- Power supply for IAEA instruments None
- Means of communication (telephone, telen, cable).
R
- Other services
- Facility personnel to escort the None Agency inspectors 7.8.3 Mode of reimbursement of the expenses charged to the Agency 4
- By cheque after receipt of the invoice by the Agency.
7.9 f,2 Tde Soecific facility health and safety rules and regulations to be observed by agency intoectors.
- As specified in paragraph 54 of the Design Information Questionnaire.
- The Agency inspectors will be informed at the facility by short briefings at the time of entry into the facility of any changes in health and safety rules or ad hoc rules as might be required in view of a special si.tuation that has occurred at the facility. For health and safety reasons, inspectors will be escorted by qualified personnel.
R Costs to be reimbursed by the Agency.
If any specific reg.est 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 expenses before the service is performed. The Agency will only reimburse such expenses if it has confirmed its initial request and agreed in writing to the amount involved which it will reimburse.
O t
.------m-
UNCLASSflED
{
Test prepared en 1986-09-24 Dato cf entry ints fccco:
193 gg g g
)
4 Facility Attachment No. 13 sat.EM' NUCLEAR GENERATING STATION, UNIT 1 Facility
- Code: UXHF / fSA Code: UXHF Page No. 19 of 19 pages
" General Agreement Code Rererence
,,.e,w, t :
- r o Reference (Articles) ggg[ g J
, (U L Q
J m.1 s
=l 11 f lis (Codes) 8.
- 30. 5.'
a aev t.t ac.
8.1 88(a)
A susunary statement will be made on the result of each inspection within 30 days of its completion.
8.2 N
88(b)
A statement on the conclusions the Agency has drawn f
from its verification activities in respect of the 1
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 1
appropriate, conclusions drawn from:
(a) Records examination; (b) Reports to the Agency; (c) Examination of containment and surveillance results; (d) Verification of inventory changes; e
(e) Verification of material accountancy; (f) Verification of the quality and functioning of operator's measurement system.
(g) Activities in resp :.t of MUF, shipper / receiver differences and/or losses.
a e
F
' l This amendment relates solely to safeguards matters and does not iavolve any significant construction impacts.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12).
Pursuant to CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
We have also concluded, based on the consideration discussed above that:
(1) there is reasonable assurance the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
The Notice of Issuance will be included in the Commission's next regular bi-weekly Federal Register notice.
Sincerely,
/s/
Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Enclosures.
1.
Amendment No. 81 to 1
License No. DPR-70 l
2.
Facility Attachment l
l cc w/ enclosures:
See next page DISTRIBUTION:
? Docket 1 File M0'Brien (2)
Wanda Jones RGallo NRC PDR OGC - Bethesda EButcher Local PDR DHagan BClayton PDI-2 Reading EJordan ACRS (10)
WButler JPartlow CMiles, GPA/PA DFischer/MThadani TBarnhart (4)
RDiggs, ARM /LFMB Previously concurred *:
Concurred by phone:
WButler[-
PDI-2/LA*
PDI-2/PM*
NMSS/LB*
OGC*
PDI-2/D M0'Brien DFischer:ca ESparks MKarman 08/13/87 08/13/87 08/12/87 08/18/87 3/2_//87 This amendment relates solely to safeguards matters and does not involve any significant construction impacts. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12).
Pursuant to CFR 51.22(b) no environmental impact statement or environmental assessment need by prepared in connection with the issuance of this amendment.
We have also concluded, based on the consideration discussed above that:
(1) there is reasonable assurance the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
The Notice of Issuance will be included in the Commission's next regular bi-weekly Federal Register notice.
Sincerely,
(
l Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Peactor Regulation
Enclosures:
l 1.
Amendment No.
to l
License No. DPR-70 2.
Facility Attachment cc w/ enclosures:
See next page l
DISTRIBUTION:
Docket File M0'Brien (2)
Wanda Jones RGallo NRC PDR OGC - Bethesda EButcher Local PDR DHagan BClayton j
PDI-2 Reading EJordan ACRS (10) j WButler JPartlow CMiles, GPA/PA i
DFischer/MThadani TBarnhart(4)
RDiggs, ARM /LFM8 Previously concurred *:
/) h, Concurred by phone-f.
PDT-T/PV NMSS/LB*
1 Ob PDI-2/D
/
Utin DFischer:ca ESparks do "NWButler M 7
g,/ib/87 08/12/87 f //[/87
/ /87
%jy1, i
I
4 1
10.
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 principle text of the US/IAEA Safeguards Agreement. The IAEA Safeguards License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License DPR-70 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 1. 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.
DPR-70 will remain in effect until the Commission notifies the licensee otherwise.
If this option is not selected by the j
IAEA, the Commission will then notify the licensee that all License Conditions pertaining to the US/IAEA Safeguards Agreement are terminated.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Facility Attachment Date of Issuance:
l l
1 i
l l
b i
h PDI-2/P OGC PDI-2/D I en DFischer:ca WButler l
7
$/i3,/87
/ /87
/ /87
,